Text

Performance Indicators, for Aug 1997
	ML20217D231
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1997
From:	; OMAHA PUBLIC POWER DISTRICT
To:	;
Shared Package
ML20217D229	List: LIC-97-0157, Forwards Fort Calhoun Station Performance Indicators Rept, for Aug 1997; ML20217D231;
References
	NUDOCS 9710030091
	Download: ML20217D231 (90)
	v • d • e

4 FORT CALHOUN STATION PERFORMANCE INDICATORS f %

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AUGUST 1997 SAFE OPERATIONS PERFORMANCE EXCELLENCE COST EFFECTIVENESS

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OMAHA PUBLIC POWER DISTRICT

FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT I

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AUGUST l

1997 i

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l Engineering and Operations Support Division

Nuclear Licensing i

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Table of Contents / Summary em TABLE OF CONTENTS /

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.lil MONTH L Y. OPE RATIN G RE PORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv W m ................................ ................ v WANO PEREORMANCE lNDEX INDICATOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vi

.WANO PERFORMANCE INDICATOR TRENDS . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . vli FORT CALHOUN STATION REPORT

SUMMARY

, . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii NUCLEAR PROGRAM GOALS AND OBJECTlH3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . lx.xil WANO PERFORMANCE INDICATORS Unit C a pa bility Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Unplanned Capability Loss Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 linplanned Automatic Reactor SCRAMS per 7000 Hours . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' 4 i

High Pressure Safety injection System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Auxiliary Feedwater System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Emergency AC Power System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Thermal P erformance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 Fuel Reliability Indmator . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 Secondary System Chemistry . . . . . . . . . , . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . , , , . . . . . . . . . . . . . 10 Collective Radiation Exposure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . , . . . . . . . . . . 11

- Industrial Safety Accident P3te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Volume of Low Level Radioactive Waste . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 SAFE OPERAT.lONS Disabling injury / Illness Cases Frequency Rate , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . . 15 Recordable injury / Illness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Clean Controlled Area Contaminations 21.000 Disintegrations / Minute per Probe Area ....,.................................... 17 Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 i

Table of Contents / Summary Safety System Failures ........................ .................... ..... . ...... 19 Maximum individual Radiation Exposure .. ........... ..... .. .............. . ...... 20 Viola tion Tre nd . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 S ig nificant E vents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Missed Surveillance Tests Resulting in LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 PERFORMANCE Station Net Generatica ............. ... .............. ........................... 25 Forced Outage R ate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 j Unit Capacity Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ ....... 27 Equivalent Availability Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 28 Unplanned Safety System Actuations I N P O Definitio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9 N R C Defi n ition . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 0 G ros s H eat R a te . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Daily Thermal Output ...................................... ....................... 32 Equipment Forced Outages per 1,000 Critical Hours . . . . . . . . . . . ........ .....,..... .. 33 Chemistry Actan Levels Exceeded Event Days . . . . . . . . . . . . . . . , . . . . . . , . . . . , . . . . . . . . . . . . . 34 Primary System Lithium % Hours Out of Limit . ......................................... 35 GCH Cents Per Kilowatt Hou r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 DIVISION AND DEPARTMENT PERFORMANCE INDICATORS Maintenance Workload Backlogs (Corrective Non-Outage) , ........ ............. ... ........ 39 Ratio of Preventive to Total Maintenance ...................... ...... ..... ... 40 Percentage of Total MWOs Completed per month identified as Rework . . . . . . . . . . . . . . . . 41 Ov e rtime . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... . 42 Procedural Noncompliance incidents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 4

In-Line Chemistry instruments Out-of-Service . . . . . . . . . . . . . . ........... ....... .... 44 il

Table of Contents / Summary l

Hazardou s Waste Produced . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 l

Contaminated Radiation Controlled Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . 46 1 1

Radiological Work Practices Program . . . . . . . . . . . . . . . . . . .............................. 47 Document Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 8 Loggable/ Reportable incidents (Security) . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . 49 Temporary Modification s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 Outstanding Modifications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 Engineering Assistance Request (EAR) Breakdown . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52 Engineering Change Notices ,

Status...................................................................53 Open.....................................................................54 Li%nsee Event Report (LER) Root Cause Breakdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 Licensed Operator Requalification Training ............................................. 56 License Candidate Exams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 57 Condition Reports . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . , . . . . . . . . . . . . . . . 58 Cycle 18 Refueling Outage l MWD Planning Status ....................................................... 59 l Overall Project States . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 l

Outage Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 -

On-Line Modification Planning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 Progress of 1997 On-Line Modification Planning ............ ,,, ,.......,..,,........... 63 i

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ACTION PLANS. DEFINITIONS. SEP INDEX & DISTRIBUTION LIST Action Pla n s . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 Performance indicator Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 66 Safety Enhancement Program index .................................................. 74 I.

Report Distrfoution List ............................................................. 76 111 i

FORT CALHOUN STATIOld AUGUST 1997 Monthly Operating Report i

OPERATIONS

SUMMARY

The Fort Calhoun Statlun (FCS) operated at a nominal 100% power until August 12,1997 at 1924 hours0.0223 days 0.534 hours 0.00318 weeks 7.32082e-4 months . At this time, reactor power was reduced to 70% due to the in operability of the Axlal Power Distribution Trip Units on "A" and "D" channels of the RPS. Operability of both channels was restored or August 14,1997 at 0413 hours0.00478 days 0.115 hours 6.828704e-4 weeks 1.571465e-4 months and

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a power ascension towards 100% was initiatled. The reactor reached 100% power on August 15,1997 at 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months . Reactor power remained at 100% until August 26, 1997 at 1215 hours0.0141 days 0.338 hours 0.00201 weeks 4.623075e-4 months when a shutdown was commenced due to the failure of the "A" Inverter (EE-8H) bypass switch. Repairs te :he switch were completed on August 26, 1997 at 2359 hours0.0273 days 0.655 hours 0.0039 weeks 8.975995e-4 months , the shutdown was stopped at 22% power and ascension towards 100%was begun. The reactor reached 100% power on August 28,1997 at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months and renained there through the end of August 1997.

During the month of August 1997, no power operated relief valves (PORV) or primary system safety valve challenges or failures occurred, iv i

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a

+ FortCalhounindexValue 8/97 OPPD Value was 88.06%

b + IndustryMedianindexValuo 2nd QRT.INPOMedianis 85.00%

100.0 .

90.0 .

83 .

85 .

= ;. r -

80.0 p - -

84 85 8'3 8'2 70.0 .

I 60.0 y 50.0 -

40.0 95/3 95/4 96/1 96/2 96/3 96/4 97/1 97/2 July August WANO PERFORMANCE INDEX TREND The Wano Perfermmce Index Trend calculation is made up of eleven variables, each value is weighted to arrive at an overallindex value. INPO calculates the Wano Performance Index value Mer: on the industry reporting the information each quarter.

The variables are calculem: e a 7 defined period of time, as listed below.

EERFORMANCE INDICATOR WElGHTED FACTOR .T.lME

' Unit Capabil;ty Factor 16 24 Months Unplanned Capability Loss F actor 12 24 Months High Pressure Safety injection 10 24 Months Auxiliary Feedwater 10 24 Months Emergency AC Power 10 24 Months Unplanned Auto Scrams /7000 Hours 8 24 Months Collective Radiation Exposure- 8 24 Months Thermal Performance Indicator 6 12 Months Secondary Chemistry Indicator 7 12 Months Industrial Safety Accident Rate 5 12 Months Fuel Reliability indicator 8 Quarterly v

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8 1a00 - g EXMMVAte r D UY 37 OAugust 97 888

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E 12.00 .

I t ~ '888 888 8 8

,o go SSS 282. S e g$ "

8 8 888 8

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8 8.00 . j f

k cn 8e8

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0.00 - - -n .e -n -n tX:F UCLF HGI AFW EAO' OE LIAS7 FR G1 m ISAR WANO PERFORMANCE INDEX INDICATORS This graph shows the difference between the Maximum No. of points for each WANO indicator and the actual value achieved by Fort Calhoun.

The current graph shows the difference between July '97 and August '97.

CALCULATED OVER A 2 YEAR PERIOD CALCULATED OVER A 12 MONTH PERIOD UCF Unit Capability Factor TPI Thermal Performance Indicator UCLF Unplanned Capability Loss Factor CPI Secondary Chemistry Indicator HPSI High Pressure Safety injection ISAR Industrial Safety Accident Rate 4 AFW Auxiliary Feedwater EACP Emergency AC Power CALCULATED OVER A QUARTERLY PERIOD UAS7 Unplanned Auto Scrams / 7000 Hours FRI Fuel Reliability indicator CRE Collective Radiation Exposure vi

.- = . .. . . . . _ - . _ - . - - . _ _ - . . . - . . . ~ . . _ _ .. . . - -

O WANO PERFORMANCE INDEX TRENDS.

(As compared to previous month) 4 4

Unit Capability Factor increased Unplanned Capability Loss Factor' Decreased High Pressure Safety injection No Change Aux. Feedwater System No Change Emergency AC Power increased Collective Radiation Exposure Increased Unplanned Automatic Reactor Scrams No Change Fuel Reliability Decreasing Chemistry Indicator Decreasing Thermal Performance increased Industrial Safety Accident Rate No Change vil

FORT CALHOUN STATION PERFORMANCE INDICATORS REPORT August 1997-

SUMMARY

POSITIVE TREND REPORT The following performance indicators A performance indicator with data exhibited adverse trends for the reporting representing three consecutive months of month.

Improving performance or three consecutive Fuel Reliability Indicator months of performance that is superior to (Page 9) the stated goalis exhibiting a positivo trend per Nuclear Operations Division Quality Maintenante Workload Backloos Procedure 37 (NOD-OP-37), (Page 39)

The foliowing performance indicators Contaminated Radiation Controlled Area (Page 46) exhibited positive trends for the reporting month:

INDICATORS NEEDING INCREASED Unolanned Automatic Reactor Scrams (Page 4)

A performance indicator with data for the Thermal Performance reporting period that is inadequate when (Page 8) ccmpared to the OPPD goal is defined as "Needing increased Management Attention" Industrial Safety Accident Rate per (NOD-OP-37).

(Page 12)

Collective Radiation Exsoosure Unolanned Eafety Svstem Actuations (Page 11)

(Page 30)

Recordable injurv/ Illness Frecuency Rate Gross Heat Rate (Page 16)

(Page 31)

Cents Per Kilowatt Hour ADVERSE TREND REPORT (Page 37)

A performance indicator with data Radioloaical Work Practices Proaram representing three consecutive months of (Page 47) declining performance or three consecutive months of performance that is trending Outstandino Modifications (Page 51) toward declining as determined by the Manager - Nucleer Licensing, constitutes an adverse trend per Nuclear Operations Division Quality Procedure 37 (NOD-OP-37). A supervisor whose performance indicator exhibits an adverse trend by this definition may specify in written form (to be published in this report) why the trend is not viij adverse.

NUCLEAR PROGRAM 1997 GOALS AND OBJECTIVES FUTURE FOCUS and RELATIONSHIP to CHANGE The nation's electric utility industry is passing through a period of significant organizational, financial and cultural changes. In this new era, change is inevitable, progress and success are not. Fort Calhoun must react to these changes while improving capacity, SALP ratings and INPO ratings.

We must KNOW OUR COSTS to CONTROL COSTS, Understanding cost is essential to controlling it, and controlling cost is essential to competing in today's market.

We are a leaming organization. We must BUILD ON OUR HIGH PERFORMANCE CULTURE.

Individuals at all levels must take responsibility for their actions and must be committed to improve their own performance.

OUR CULTURE MUST SUPPORT THE NEW STRATEGIES. We must continue to develop and implement strategies that will allow us to effectively compete in the evolving market while still maintaining the highest levels of safety and reliability Communicating is our key to improving. Follow up and feedback must be candid, forthright and timely.

We recognize that change causes disruption of work and work flow. That change requires increased management direction. We need IN-DEPTH, RELENTLESS ATTENTION to our NEW FOCUS / STRATEGIES.

VISION To be recognized as the best nuclear organization in tne world and to preserve nuclear energy as a viable future energy source.

MISSION The safe, reliable and cost effective generation of electricity for OPPD customers through conservative decision making and the professional use of nuclear technology. We will conduct these operations to assure the health, safety, and protection of our personnel, the general public, and the environment.

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GQALS Goal.1: SAFE OPERATIONS Supports: April 1996 Corporate Strategic Plan Goal 3, Objective: 3 & 4 A proactive, self-critical and safety conscious culture is exhibited throughout the nuclear organization. Individuals demonstrate professionalism through self-ownership and personal initiative and open communication.

1997 Priorities:

. Achieve an overall SALP Rating of *1"in 1997,

. Focus on Achieving an INPO Rating of '1" in 1998.

Reduce 1997 NRC violations with no violations more severe than level 4.

No unplanned automatic reactor scrams or safety system actuations.

Objectives to support SAFE OPERATIONS.

OBJECTIVE l-1:

No challenges to a nuclear safety systems.

OBJECTIVE l-2:

Comply with n ,'plicable policies, technical specs, procedures, standing orders and work instructions.

OBJECTIVE 1-3:

Identify conditions BEFORE they affect plant safety and reliability. Address every cafety concern.

OBJECTIVE 14:

Achieve all safety-related 1997 performance indicator goals in the Performance Indicator Report.

OBJECTIVE 1-5:

Zero Lost Time injuries and recordable injuries rate BELOW 1.5 percent.

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..O-OPPD NUCLEAR ORGANIZATION GOALS 1997 Priorities

{

, 1 Goal 2:- PERFORMANCE

]

j Supports: ' April 1996 Corporate Strategic Plan Goal 3l Objective: 2; G-4, Objective: 1,2, &

, 3; G-5, Objective: 2 .

]

[ Nhclear teamwork achieves high performance at Fort Calhoun Station as exhibited by l safe, reliable and cost effective power production.

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! 1997 PRIORITIES:

.= improve Quality, Professionalism and Teamwork.

. Maintain High Plant Reliability, p . Pursue efficient, cost-effective work processes.

[ .. _ Meet or exceed INPO key parameters.

Reduce the number of Human Performance errors.

L . Identify Programmatic performance problems through effective self assessment.

-. Maintain a high level of readiness in the ERO.

Objectives to support PERFORMANCE: >

l- OBJECTIVE 2-1:

iL 1..

Achieve an annual plant capacity factor of 92.7% and a unit capability factor of 96.0%

- OBJECTIVE 2 2:

I Training meets the_needs of the plant and the National Academy accreditation objectives.

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.. Line managers use training to present, discuss & reinforce performance standards.

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. Line managers monitor and assess personnel performance to determine how well l . standards are met.

.-- . Line managers through personal involvement in training emphasize the importance of

, conducting activities within approved procedures / practices. ,

F . Executive Training Committee:

=+ invites line supervisors to discuss the direction training is going for their specific

. area.

4 invites the line and training supervisors responsible for each accredited program j i- to provide a status of intamal accreditation assessments.

+ ensures items such as training attendance, attentiveness, punctuality, etc. are i uniformly emphasized.-

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. _ _ __ _ ~ _. __ _ _

OPPD NUCLEAR ORGANIZATION GOALS 1997 Prioriting Goal 2: PERFORMANCE (Continued)

OBJECTIVE 2 3:

Achieve all performance-related 1997 performance Indicator goals in the Performance Indicator Report. Focus on performing basic skills well, while pursuing efficient, cost-effective work processes. Identify the barriers to excellence and resolve them.

OBJECTIVE 2-4:

Plan for the completion of the 1998 refueling outage in 42 days of less.

OBJECTIVE 2 5:

Teamwork is evident by improved plant reliability, an effective emergency response organization, reduced number of human performance errors and effective self assessment.

Goal 3: COSTS Supports: April 1996 Corporate Strategic Plan Goal 2, Objective: 1, 3, and Goal 5, Objective: 1 Operate Fort Calhoun cost effectively to contribute to OPPD's " bottom line". Cost

consciousness is exhibited at all levels of the organization.

1997 Priorities:

. Maintain total O&M and Capital Expenditures within budget.

Streamline work process to improve cost effectiveness.

= lmplement Opportunity Review recommendations.

Objectives to support COSTS:

OBJECTIVE 3-1:

Conduct the nuclear programs, projects, and activities within the approved Capital and O&M budgets.

OBJECTIVE 3-2:

Significantly reduce operating costs through full support of Utilities Service Alliance initiatives by maximizing sharing of resources, leveraging of buying power and elimination or reduction of redundant support services.

Goals Source: Lounsberry (Manager) xii

4 9

WANO PERFORMANCE INDICATORS 1

Oczthly U340 03pgbility Pgst.t

... ... n ouvi v18e e.g. mi, r..i.t

+ 1697 r<*rt Calhese este (94%)

_ _; Ye at 2000 W ANO lnavstry 0.el (47%)

120% ..

$$A% 100.0 % 100.0% 100.0% 100.0% 100.0 % g g,4 g

.k b 00% .. t i.7% . ...b

. . . . . . .. .. . ... .. . . . .x m15. . . . . . . . . . . m. .. . . .. .

43.7%

40% -

0.7 %

0% e M Sep Oct Nov Dec Jan Feb Mar Apr May June J uly Aug UNIT CAPABILITY FACTOR This indicator shows the plant monthly Unit Capability Factor (UCF) value, a rolling 12-month average, the OPPD goal, and the WANO 2000 goal. UCF is defined as the ratio of the available energy generation over a given period of time to the reference energy generation over the same time period, expressed as a percentage.

The UCF for August 1997 was repoded as 95.4%. The year-to-date UCF was also reported as 73.4%, the UCF for the last 12 months (September 1996 through August 1997) was 72.9%, and the 36-month average (September 1994 through August 1997) was reported as 81.3%.

Energy Losses-Forced Outage -Circumferentici cracking of a weld down stream of a moisture separator due .o high syste.m stresses, Event Period: May 28 thru May 291997.

Forced Outage - SNm leak in the hurth stage extraction steam system, Event Period: April through mid May 1997.

Forced Outage - Due to a steam leak in the fourth stage extraction steam system, Event Period: April 1997.

. 1996 Refueling Outage, Event er r iod: Sept through Nov.1996 -

. Forced Outage - MOV-CV 'eakage, Event Period: Dec.1996 The Year 2000 WANO industry goal is 87% and the industry current best quartile value is approximately 85%. Th.e 1997 Fort Calhoun annual goal for this indicator is a minimum of 96.0%.

The maximum index print value for this indicator is 16. At the end of the August 1997, the FCS Value was 12.49 This compares to the previous month's value 12.48.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: None 2

a Monthly Unplanned Capability Loss Factor

_ 1244onth RolHng Average

-e_ Fort Calhoun Ooal (1.58%)

+ Year 2000 WANO lndustry Goal (4.5%)

80% . S& 30 %

50% .

O- 30.42 % 30.50 %

30% - - -

20% + 1.57 % am 0.00 % a00% a00% 400% N 0.00 % .

10%-. a00%

C :

^

_,, - w w ; ,

0% h ,

h %- =ms hrm= 4 .4_. _ _4 4 Sep oct Nov Dec Jan Feb Mar Apr May June July Aug UNPLANNED CAPABILITY LOSS FACTOR This indicator shows the plant monthly Unplanned Capability Loss Factor (UCLF), a rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal. UCLF is defined as the ratio of the unplanned energy losses during a given period of time, to the reference energy generation expressed as a percentage. Unplanned energy loss is defined as energy not produced as a result of unscheduled shutdowns, outage extensions, or !oad reductions due to causes under plant management control. Energy losses are considered to be unplanned lf they are not scheduled at least four weeks in advance.

The UCLF for the month of August 1997 was reported as 4.6%. The year-to-date UCLF was 14.7%, the UCLF for the last 12 months (September 1996 through August 1997) was 9.92%, and the 36-month average UCLF (September 1994 through August 1997) was reported as 8.5% at the end of the month.

The Year 2000 WANO industry goal is 3.0% and the industry current best quartile value is approximately 3.2%. The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.58%.

The maximum index point value for this indicator is 12. At the end of August 1997 the FCS Value was 11.96. This compares to the previous month's value of 12.00.

Data Source: Generation Totals Report & Monthly Operating Report Accountability: Chase Trend: None 3

l 1

-e 12-Minth Ralling Av:r:ge e

j

+ FCS R;;ctir Scrams P;r 7.000 Haurs Critic t fit 1:st 36 months Fart Cilh:un Csil(0.0) I c., Yeer 2000 WANO Industry G oal(1) 3 .-

2 -

1

-w. . . . . . .

0 : : : : i i i i 5 5 5 Sep Oct N ov Dec Jan Feb M ar Apr M ay June Juh Aug FCS Reactor Scrams .1997 i

4 .-

3 .

4 2..

1-0 0 0 0 0 0 0 0 o o o o o o 96 Aug Sep . oct Nov Dec Jan Feb Mar Apr May June July Aug

, UNPLANNED AUTOMATIC REACTOR SCRAMS PER 7000 HOURS CRITICAL The upper graph shows the 12-month rolling average, the 36-month average, the OPPD goal for 1997 and the Year 2000 WANO goal. The lower graph shows the number of unplanned automatic reactor scrams that occurred during the last 12 months. This indicator is defined as the number of unplanned automatic scrams that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of critical operation.

There were no unplanned automatic reactor scrams during the month of August 1997.

The 12-month rolling average (Septemb^r 1996 through August 1997) was 0. The 36-month value (September 1994 through August 1997) was 0.310.

The 1997 Fort Calhoun Station goal for this indicator is 0. The Year 2000 WANO industry goal is a maximum of one unplanned automatic reactor scram per 7,000 hours0 days 0 hours 0 weeks 0 months critical.

The maximum index point value for this indicator is 8. At the end of the August 1997, the FCS Value was 8.0. This compares to 1.ie previous month's value of 8.0.

Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability: Chase Trend: Positive 4

gg Monthly HPSI Systsm unavailability Value .

w 12 Month Polling Av:rsgo

-. Fort Calhoun Goal (0.003) 7 Year 2000 WANO Industry Goal (0.02) 0 02 -- e a a a : a : a 1 0.015 -

O.01 .

O.005 .

: : : : : : : : : o C _

^ - >

4 sep Oct Nov Dec Jan Feb Mar Apr May June July Aug HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the High Pressure Safety injection (HPSI) System unavailability value, as defined by INPO in the Safety System Performance Indicator Definitions, for August 1997.

The HPSI System unavailability value for the month of August 1997 was 0.0. There were 0.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of planned unavailability, and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability, during the month. The 12 month rolling average was (September 1996 through August 1997) was 6.66E-5, and the year-to-date HPSI unavailability value was 9.8xE-4 at the end of the month.

For the previous year there was a total of 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of planned unavailability and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability for the HPSI system.

The 1997 Fort Calhoun year-end goal for this indicator is a maximum "ue of 0.003. The Year 2000 WANO industry goal is 0.02.

i . The maximum index point value for this indicator is 10. At the end of August 1997 the FCS Value was10. This compares to the previous month's value of 10.

Data Source: Phelps/Schaffer (Manager / Source)

Accountability: Phelps/Schaffer Trend: None 5

%1 n F a'v la liity T YearNNNONfu hGoal(0.025) 0.025 ,. 0.022 j l

O 02 + C : L a ; ; ; a 1 0.015 0 01 + : : : : : 1 : :

0.228 0.111 0.005 . -

x -x 0.166 0 , p x- D 0 E,O GM 1 1 m,E ,

1997 Sep Oct Nov Dec Jan Feb Mar Apr May June July Aug AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE This indicator shows the Auxiliary Feedwater (AFW) System Unavailability va!ue, as defined by INPO in the Safety System Performance Indicator Definitions, for the month of August 1997.

The AFW System Unavailability Value for August 1997 was 0.0 hours0 days 0 hours 0 weeks 0 months . There were 0.0 hours0 days 0 hours 0 weeks 0 months of planned and 5.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of unplanned unavailability during the month. The 12 month rolling average (September 1996 through August 1997) was 0.0045, and the year-to-date unavailability value was 0.0050 at the end of August 1997.

The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 0.01.

The Year 2000 WANO industry goal is 0.025.

The maximum index point value for this indicator is 10. At the end of August 1997, the FCS Value was 10. This compares to the previous month's value of 10.

Data Source: Phelps/Fritts (Manager / Source)

Accountability: Phelps/Fritts Trend: None 6

m (2tnthly Emergency AC Prwer Unavtilability V:lus '

-x- Year.t>Date Emergency AC P wer Un:vcilability Valu)

Fort Calhoun Goal (0.024)

OM - --er Ye er 2000 WANO Industry Goal (0.025) ,

0.035 -

0.03 -

0.025 -

0.02 7

0.015 --

0.01 -- x x "

x x x *7g 0 005 0.002 Sep Oct Nov Dec Jan Feb Mar Apr May June Aug Juh EMERGENCY AC POWER SYSTEM SAFETV SYSTEM PERFORMANCE This indicator shows the Emergency AC Power System unavailability value, as defined by WANO in the Salety System Performance Indicator Definitions, for the month of August 1997.

The Emergency AC Power System unavailability value for August 1997 was 0.005. During the month, there were 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of planned unavailability (3.1 for DG-1 and 4.4 for DG-2), and 0.0 hours0 days 0 hours 0 weeks 0 months of unplanned unavailability for testing and repairs. The Emergency AC Power System unavailability value year-to-date was 0.012 and the value for the last 12 monts (September 1996 through August 1997) was 0.009.

There have been 140.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months year to date,58.15 for DG-1 and 82.15 for DG-2, of planned unavailability and 0.0 nours of unplanned unavailability for the emergency AC power system in 1997.

There were a total of 188.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of planned unavailability and 3.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months of unplanned unavailability for the emergency AC power system in 1996.

The 1997 Fort Calhoun year-end goal for this indicator is a maximum value of 0.024. The Year 2000 WANO industry goal is 0.025.

The maximum index point value for this indicator ir 10. At the end of August 1997, the FCS Value was 10.00 This compares to the previous month's value of 7.88.

Data Source: Phelps/Ronning (Manager / Source)

Accountability: Phelps/Ronning Trend: None 7

l

, , Monthly ThermalPerformance

. .12 Month Rolling Average Fort Calhoun Goal (99.6%)

o Year 2000 W ANO Industry Goal (99.5%)

100% _ _ _

7 - -

2 7, 7

b- _

m l :

8.-

K

~

k~

g l

.,- y l

p

g. .

99% .

[* i s E

I( $

4u.

h w e, g P n,

.1 1996

, is 1 f.I s

nro ,

f E

}. .

4 R : 4 11 j!

i r ? .; n w<

N j

l d p"I a

98 % , Y D I 8 } $ 4 3 $ I I j .i I THERMAL PERFORMANCE This indicator shows the monthly Thermal Performance Value, the rolling 12-month average, the OPPD goal, and the Year 2000 WANO goal.

The thermal peiformance value for the month of August 1997 was 100%. The year to date value was reported as 99.9%. The 12 month ro!!!ng average (September 1996 through August 1997) was reported as 99.8%.

The 1997 Fort Calhoun year-end goal for this indicator b an index value which is > 99.7%.

The Year 2000 WANO Industry goal is 99.5%.

The maximum index point value for this indicator is 6. At the end of August 1997, the FCS Value was 6.00 This compares to the previous month's value of 5.55.

Data Source: Phelps/Naser(Manager / Source)

Accountability: Phelps/Naser Trend: Positive

. 8

=='

._._4.......

/. '. ' '.". : " 'J. ..m".

. . . ','. i . . . . . . ,, . . . . . . . . . . , . . . . , .

... ,2 . . a .

I!... t

" 'o' I

z ; %5 d

. 'fd

, E 'A5 51 [b i 3 a 5 4 ! 1 1 i i t i FUEL RELIABILITY INDICATOR A fuel vendor provided failure prediction update for August has not yet been received. Based on the reactor coolant activity data through July 31,1997, the current fuel failure prediction is 27 fuel failures at lower core power levels. The cesium data indicates the leaking fuel to be in a mixture of second and third cycle bumed fuel (Batches S and T) which have the original grid design. The monthly FUEL RELIABILITY INDICATOR (FRI) for August 1997 was 61 x E-04 microcuriess/ gram.

The monthly FUEL RELIABILITY INDICATOR (FRI) for August 1997 was 61xE-04 microcuries/ gram based on steady state data from August 1 through 12 and 19 though 26,1997.

This is an increase from the July 1997 FRI of 45 x E-04 microcuries.

The Cycle 17 monthly FRI is trending lower than the Cycle 16 FRI at the same time in the fuel cycle due to the large contribution of the lodine-134 from the "recoll" Uranium. The lodine-134 activity is released to the coolant from the recoil activity that is plated out on fuel assembly surfaces due to fuel failures in prior cycles. In the FRI equation, the lodine-134 activity is subtracted from the lodine-131 activity. This cycle, the recoil activity is trending two times higher than Cycle 16 while the lodine-131 is trending similar to the Cycle 16 values at the same point in the cycle.

Consequently, the Cycle 17 calculated FRl value is trending lower.

The plant !s currently in Action Level 2 Standing Order SO-0-43, Fuel Reliability Action Plan, based on the July prediction of 10 core average power failures.

Based on the number of predicted fuel failures at lower core power levels and the expectation that future fuel failures will be identified, this performance category is to be considered POOR for the second quarter of 1997.

The 1997 Fort Calhoun Station FRI Performance Indicator goalis to maintain FRI below 147 E-4 microcuries/ gram. This goalis based upon previous cycles fuel performance, results of the most recent fuel inspection and reconstitution campaigns, and an improved fuel failure resistant grid design in the new assemblies (Batch U)in the Cycle 17 core.

The maximum index point value for this indicator is 8. At the end of the August 1997, the FCS Value was 1.32. This compares to the previous month's value of 2.13.

Data Source: Guinn/Guliani Accountability: Chase /Stafford Trend: Adverse 9

l

m MonthlyChemistryindicator

+ Fort Calhoun Gomi(1.4)

I 2.6 W i

2.5 --

2.4 --

2.3 -

l 2.2-2.1 y 2.-

1.9 --

1.8 --

l 1.7 -

1.6 --

1.5 - 1.31 1.18 1.32 1.27 3m

, 1.4 . . - - - .

j,'2 ~~ 1.15 1.14 g,33 i -

d1.1T: Sep Oct Nov Dec Jan Feb IIil Mar Apr May June July Aug l

l f

1 -

l SECONDARY SYSTEM CHEMISTRY

Criteria for calculating the Secondary System Chemistry Performance Index (CPI) are as follows

l 1) the plant is at greater than 30% power.

2) the power is changing at less than 5% per day.

i The CPI for August 1997 was 1.32. The CPI value for the past 12 months (September 1996 through August 1997) was 1.09. The CPI value in the industry's upper quartile is 1.17.

Six parameters are used in the CPI calculation. Four of the parameters were below the INPO mean i value which are as follows: 1) steam generator chloride,2) sulfate,3) feedwater iron, and condensate j pump discharge dissol.ed oxygen. Steam Generator sodium was above the mean value and has remained unchanged from the previous month. FH-6 copper remains above the INPO mean but is

, lower than the previous months value.

The maximum index point value for this indicator is 7. At the end of August 1997, the FCS Value was 5.29. This compares to the previous month's value of 5.39.

I Data Source: Hamilton /Ostien (Manager / Source Accountability: Hamilton Trend: None j 10 I

ggg MonthlyPersonnelRedationExposure .

e_. CumulatNo PersonnelRnJWlon Exposure

+ ICSGoal3r anoMBI 40 ,

0 0 0 0 0 0 0 0 0 0 o

{

30 +

l25 e 20 .

b 15 .

1.734

" 3.785 3.364 O re 1 5 H rm en . ,

Jan Feb Mar Apr May Jun Jd Aug Sep Oct Nw Dec COLLECTIVE RADIATION EXPOSURE The 1997 Fort Calhoun goal for Collective Radiation Exposure is set at 38.0 person REM.

The exposure for August 1997 was 3.364 Person-Rem (ALNOR).

The year-to-date exposure through the end of August 1997 was 27.041 Person-Rem (ALNOR).

s This indicator is a " COLLECTIVE" indicator. WANO does not differentiate between on-line and outage exposure.

The Year 2000 WANO industry goal for collective radiation exposure is 120 person-rem per year. For the three year period (Soptember 1994 through August 1997), the total collective radiation exposure is 402.06 person-rem (ALNOR). The Fort Calhoun Station annual average over 3 years was 134.02 person-rem per year (A.U 40R).

The maximum index point value for this indicator is 8. At the end of August 1997 the FCS Value was 8.00 This compares to the previous month's value of 7.21.

Data Source: Chase / Williams (Manager / Source)

Accountabill:y: Chase /Gebers Trend: Needing Increased Management Attention SEP54 11 5

+ Monthlyindustrial Accident Rate

+ 12 Month Rolling Averego

+ FCS Year 4.nd Goal (<0 50)

+ Year 2000 WANO industry Goal (<0.40) 1.2 .

1 0.8.

R _ _ _ _ _ _ _ _ _

O.4 I TNE " ! ! ! ! ! !

~ " ~ ~ " "

0l "N= = =

- : : : : : : ----e Sep Oct Nov Dec Jan Feb Mar Apr May June July Aug INDUSTRIAL SAFETY ACCIDENT RATE The purpose of this indicator is to monitor progress in improving industrial safety performance for utility personnel permanently assigned to the station. Contractor work-hours are not included in the indicator. This indicator is defined as the number of accidents por 200,000 work-hours worked for all utility personnel permanently assigned to the station that result in any of following:

One or more days of restricted work (excluding the day of the accident.)

+

One or more days away from work (excluding the day of the accident.)

Fatalities.

ISAR = (number of restricted-time accidents + lost-time accidents + fatalities) x 200.000 (number of station person-hours worked)

. The Fort Calhoun Station industrial safety accident rate for the month of August 1997 was 0.00. The 12 month rolling average (September 1996 through August 1997) was 0.0794.

The year to date value was 0.00 at the end of August 1997.

There were no restricted-time and no lost-time accidents in August 1997. The 1997 Fort Calhoun year-end goal is 50.50. The Year 2000 WANO industry goal is 50.40. The maximum index point value for this indicator is 5. At the end of August 1997, the FCS maximum index point Value was 5.0 This compares to the previous month's maximum l

index point value of 5.0.

Data Source: Sorensen/Bluni9nthal (Manager / Source)

Chase / Booth (Menager/ Source)

Accountability: Chase / Bishop Trend: Positive l 12

i m , - C.t o nthly Volu m o of LLQ W (c u. f t.) .

-u- Ye ar.to.D oto C u m ulativ e R e disactiv e W a ste B urie d

--.e-.- F o rt C alh o u n G o al (1200 cu.f t.)

1200 : : : : : : : : : : : --

1100 --

1000 --

900 --

800 y 700 .

600 +

500 --.

400 --

300 - , $ $

200 +l , g 5 x

, p, 100 __ 8 e~

x m R

x.

'*p*IWI 2

ran O _x -

? $ 5 5 $ k A $ $ E E $

VOLUME OF LOW-LEVEL RADIOACTIVE WASTE This indicator shows the volume of the monthly Radioactive Waste buried, the cumulative year-to-date radioactive waste buried, and the Fort Calhoun goal.

Cu. Ft.

Amount of solid radwaste shipped off-site for processing during cmTent month 00.0

- Volume of solid radwaste buried during August 1997 20.4 Cumulative volume of solid radioactive waste buried in 1997 192.3 Amount of solid radwaste in temporary storage 251.2 The 1997 Fort Calhoun Station goal for the volume of solid radioactive waste (buried) is 1200 cubic feet. The Year 2000 WANO industry goal is 45 cubic meters (1,589 cubic feet) per year. The industry upper ten percentile value is approximately 27.33 cubic meters (965.3 cubic feet) per year.

This indicator is no longer used by INPO The indicator will still be tracked, but will no longer be used in computing the Station's Index Number.

Data Source: Chase /Breuer (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP54 13 l

l l

i SAFE OPERAT ONS i

i i

l Goal: A proactive, self-critical and safety conscious culture j is exhibited throughout the nuclear organization. Individuals l demonstrate professionalism through self-ownership and l personalinitiative and open communication.

l i

i l

l 1

}

t i

t 14 l

I i

i<

e e

Con ::ly Disabling injury / Illness Frequency

+ 12 Month Rolling Average 1997 F.C.S. Goal 2,

1.8 -

1.6 --

1.4 -

1.7 --

1 7

0.8 ..

l - . . . . . . . . .

0.4 -- I ! -* I I O.2 .

0 . : : : : : : :

Sep Oct Nov Dec Jan Feb Mar Apr May June July Aug DISABLING INJURY / ILLNESS FREQUENCY RATE (LOST-TIME ACCIDENT RATE)

This indicator shows the August 1997 Disabling Injury /lliness Frequency Rate and the disabling injury / illness rate for the past 12 months (rolling average).

For the month of August 1997 the disabling injury / illness frequency rate was 0.00. For the 12 monthperiod (September 1996 through August 1997) the disabling injury / illness rate wm 0.16.

There were no disabling injury / illness cases reported for August 1997.

The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 0.5.

Data Source: Sorensen/Blumenthal (Manager / Source)

Accountability: Chase / Bishop Trend: None SEP 25,26 & 27 15

r.

I

Conthly Recordable injuryfillness Froquency Rate

+ Rolling 12 Month Aw; rage

........ Fort Calhoun Goal 4.5 4.0 -

3.5-3.0 2.5--

2.0 W e- .

1.5 e . . . . . . . . . e . . . . . . . . . e . . . . . . . . e- . . . . . . . . e . . . . . . . . . e . . . . . . . .... .: = " .. . . $. . . . . . . . .s h4 1.0 Sep oct Nov Dec Jan Feb Mar Apr May June July Aug RECORDABLE INJURY /lLLNESS FREQUENCY RATE This indicator shows the monthly Recordable injury /lliness Frequency Rate, a rolling 12 month average, and the OPPD goal. A recordable injury / illness case is reported if personnel from any of the Nuclear Divisions are injured on the job and require corrective medical treatment beyond first aid. The recordable injury / illness cases frequency rate is computed on a rolling 12 month average.

The recordable injury / illness frequency rate for the month of August 1997 was 1.72.

The recordable injury / illness frequency rate for the past 12 months (September 1996 through August 1997) was 1.55.

During the month of August 1997, there was no recordable injuries. There has been a total of 7 recordable injury / illness cases in 1997.

The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.5.

Data Source: Sorensen/Blumenthal (Manager /Sou rce)

Accountability: Bishop Trend: Needing increased Management Attention SEP 15,25,26 & 27 16 l

m Contamination Ev:nts(Monthly)

-c Contamination Events (YTD) 100.

90 -

80 d 70 -

60 .

50 .

40 41 41 40 . - e 31 24 20 +

10 '+ -

0 -

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec CLEAN CONTROLLED AREA CONTAMINATIONS 21,000 DISINTEGRATIONSIMINUTE PER PROBE AREA This indicator shows the Personnel Contamination Events in the Clear Controlled Area for contaminations 21,000 disintegrations / minute per probe area for August 1997.

There was O contamination event in August 1997. There have been 41 contamination events in 1997 through the end of August 1997.

Data Source- Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None SEP 15 & 54 17

I miE;g PersonnelErrors (Esch Conth) ,

.+ Pro i:ntable (18-Month Totals)

--e Personnel Error (18. Month Totals) 20 .

15 .-

10 -

MN: 1/

,_ / N . .. .

" ~ ~

~

[ C C E

O 4 ' E N N > II Feb Mar Apr Way Jun Jul Aug Sep oct Nov Dec Ja s Feb Mar Apr May June July PREVENTABLE / PERSONNEL ERROR LERs This indicator depicts 18-month totals for numbers of " Preventable" and " Personnel Error" LERs.

The graph shows the 18-month totals for preventable LERs, the 18-month totals for Personnel Error LERs, and the Personnel Error totals for each month. The LERs are trended based on the LER event date as opposed to the LER report date.

NOTE: Due to the way LERs are tracked & reported, this indicator is one-month behind.

In July 1997, there was one event which was subsequently reported as an LER. No LER's were categorized as Preventable and no LERs were categorized as Personnel Error for the month of July. The total LERs for the year 1997 is nine. The total Personnel Error LERs for the year 1997 is two.

The 1997 goal for this indicator is that the year-end values for the 18-month totals not exceed 12 Preventable and 5 Personnel Error LERs.

Data Source: Tills /Cavanaugh (Manager / Source)

Accountsbility: Chase Trend: None SEP 15 18

i i Strtup m Shutdown m Operations

...o... Industry Average Trend 2 ..

c l 1.5 4 u.

% 1y -

0.5 - .....O... . ,. ....G~+~.0- .

.O. ~O~ ~ . D . . . . . .a 93 1 C3-7 93 3 93 4 94 1 94 2 94 3 S4-4 95 1 95-1 95-3 95-4 Year-Quarter

, GAFETY SYSTEM FAILURES This indicator illustrates the number of NRC Safety System Failures as reported by the Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data in the annual" Performance Indicators for Operating Commercial Nuclear Power Reactors" report.

The following safety system failures occurred between the 2nd quarter of 1992 and the 1st quarter of 1995:

1st Quarter 1993: The SG low pressure scram signal block reset values, for all 4 channels of both SGs, were greater then the allowed limits. This rendered the scram input inoperable at certain operating conditions.

2nd Quarter 1993: A section of the piping configuration for the borated water tource of the safety injection system was not seismically qualified. This could have resulted in a failure of the system to meet design requirements during a seismic event.

4th Quarter 1993: 1) During surveillance testing, both PORVs for the LTOP system failed to open during multiple attempts. The failums were a result of differential expansion caused by a loop seal, excessive venting line back pressure, and cracked valve disks; 2) Calibration errors of the offsite power low signal relays could have prevented offsite power from tripping and the EDGs from starting in the required amount of time during a degraded voltage condition; 3) Both AFW pumps were inoperable when one was removed from suvice for testing and the control switch for the other pump's steam supply valve was out of the auto position.4) Only one train of control room ventilation was placed in recirc when both toxic gas monitors became inoperable.

Later during surveillance testing, the other train auto-started and brought outside air into the control room for a six-minute period.

1st Quarter 1994: A design basis review determined that an ESF relay could result in loss of safety injection and spray flow, due to premature actuation of recirculation flow.

4th Quarter 1994: An accident scenario was identified that could result in the inoperability of both control room air conditioning units. Following certain accident conditions, CCW temperature could rise causing compressor rupture disc failure and a relense of freon.

There were no safety system failures since the 4th quarter of 1995.

Data Source: Nuclear Regulatory Commission Accountability: Chase Trend: None 19

gyggHighest Monthly indMdual Exposur) mR ,

g-- gHigh:st indMdu:1 Exptsura Year-to-dats mR

+ FCS Annual year-end ooal 1000 mR/indMdual 1000 : : : : : : : : : : : :

900 -

800-700-600 -

~ ~

500-400 300 200.

100-O.

Jan Feb M ar Apr May Jui Jul Aug Sep Oct Nov Dec MAXIMUM INDIVIDUAL RADIATION EXPOSURE This indicator shows the highest exposure for an individual during the year 1997.

For the month of August 1997, an individual accumulated 593 milllRem, which was the highest individual exposure for the month.

For the year to date, an individual has accumulated a total of 705 milllRem (TLD). The 705 milllRem came from ALNOR readings, and in general, are higher than TLD readings.

The 1997 Fort Calhoun Station Annual Administrative year-end goal is a maximum of 1,000 millirem from all sources of occupational exposure at FCS. The OPPD limit for the maximum yearly individual radiation exposure is 4,000 milllRem/ year from all sources of occupational exposure.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: None 20 l

l

m Pc6 Cned Vielgtions (Zenthly)

+

a Pc8 Non Ched Vietstione (Zonthly) e _ PCSCitedViolations(184enth Average)

+ PCS Non CNed Violations (184onth Average) i e Region IV Cited Violations (13-Month Average for Mepion IV top quartile) '

12 -

10 - _ : : :

g

s. -

,. 9 = = = = =

g

- 3 !

4- c : : : : : : = w a

{

~

l~I *

"% g p sep oct Nov Dec . Jari Peb Mar Apr May June July Aug VIOLATION TREND This indic:%r illustrates a 12 month trend for Fort Calhoun Station Cited Violations. Non.

Cited VioWna and Cited Violations for the Top Quartile plants in Region IV. Additionally, the Fort Calhoun Station Cited and Non-Cited Violations for the past 12 months will be illustrated monthly. The 12-month trend for the Region IV top quartile lags 2-3 months behind the Fort Calhoun Station trend. This lag is necessary to compile information on other Region IV p' ants, b

he followlog inspection reports noting violations were received during August 1997:

Violation Laval lER.No, Title IV (1) 97 09 Special Inspection. Steam Line Rupture IVv (?) 97-15 Resident Monthly inspection To date, OPPD has received zero violations for inspections completed in the current SALP cycle.

Level 111 Violations 0 LevelIV Violations 0 Non-Cited Violationg Q Total 0 The 1997 Fort Calhoun Station Goal for this performance indicator is to be at or below the cited violation trend for the top quartile plants in Region IV.-

Data Source: Tills /Cavanaugh (Manager / Source)-

Accountability: Tills Trend: None 21

e m HRC sintificant Everts 12d etr/ Aver;g) Tr;nd

.-e J 1 1 1

0.$ -

Ow W --- ,- M - m - , - -- -

m - o- . rm .a a _ f; 93 93 94 96 1 96 3 98 3 96 4 98 1 $ N' $$.3 98-4 Ye ar . Quarte r INPO Significant Events (SEs) 3 3

2- 1 1 j_ ..

mm ' ' '

93 94 96 1 96 2 96 3 96-4 96 1 96 2 96 3 96 4 97 1 i Year-Quarte r i

NRC SIGN!FICANT EVENTS The following SEs were identified between the 2nd Quar'at of 1992 and the 151 quarter of 1995 (as reported in ttw NRC's

' Performance Indicators for Operating Nuclear Power rasctors' report dated June 30,1995):

3rd Quarter 1992: The failure of a Pressurizer Code Safety Valve to resent initiated a LOCA with the potential to degrade the reactor coolant pressure boundary, 4th Quarter 1994: A potential accident scenario involving a large break LOCA or a main steam line break inside containment ets'd result in the inoperability of both control room A.C. units.

INPO SIGNIFICANT EVENTS Tha following SEs have been identified since 2nd Quarter of 1902 by INPO:

2nd Quarter 1992: Intake of transuranics during letdown filter change-out.

3rd Quarter 1992: Safety Valve malfunction (RC-142).

1st Quarter 1993: Inoperability of Power Range Nuclear Instrumentation Safety Channel D, 2nd Quarter 1993: Inadequate control of Switchyard activities.

3rd Quarter 1993: Loss of reactor coolant due to malfunction of Pressurizer Safety Valve.

1st Quarter 1994: 1) Unexpected CEA withdrawal. (Event occurred November 13,1993 but was not identified as an SE until 1st Quarter 1994).

2) Unplanned dilution of Boron concentration in the Reactor Coolant System.

1st Quarter 1996: During pressurizer solid plant operation. the Low Temperature Overpressurization (LTOP) protectx>n for the RCS was inadvertently disabled.

2nd Quarter 1996: RC Pump Anti-Reverse Rotation Device (ARD) failure.

No SE reports have been received from INPO on the 1996 SEs as of August 1, 1996.

Data Source: Nuclear Regulatory Commission & INPO Accountability: Chase Trend: None 22

Meeed STs Resulting in LIRs 3

I 2.

1 0 -

1

M : , ; , ;

96 Jan Feb Mar Apr Nhry Jun JLA Aug Sep Oct Nw Dec I 1 NUMBER OF MISSED SURVEILLANCE TESTS ,

RESULTING IN LICENSEE EVENT REPORTS j This indicator shows the Number of Missed Surveillance Tests (STs) at FCS, that resulted in Licensee Event Reports (LER)s during August 1997.

There were no missed surveillance tests resulting in LERs during July 1997.

The 1997 Fort Calhoun monthly goal for this indicator is 0.

Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability: Chase /Phelps Trend : None SEP 60 & 61 23 i

i i

PERFORMANCE Goal: To strive for Excellence in Operations utilizing the highest standards of performance at Fort Calhoun Station that result in safe, reliable plant operation in power production.

24

Net Generation (10,000 MWh) 40 ,

36.29 35.14 34,g 35.1 34.43

~

32.52 -

3 so.os k [5j !$ I 30 y- ,f

,r h n E 1996 24.37 g' N; h h l# I is.s4 '[ $

i d ilF -

2 M

? Y ((

, , d @l l

'O f .(

b sf G.748 w ! ;

kj IN

.6) t,

'. c p?{

's l if h

[e " '

h. hk ![; 4 '- '.

e av i W W:* ;

's i Of g is . , . 94 4}O e- +

i glU .: e .4, E C l", $l% 0. . ~ ,

l 5 E $ $ k $ 5 5 $ k $ $'

STATION NET GENERATION During the month of August 1997, a net tc'.al of 338413.4 MWh were generated by the Fort Calhoun Station. Cumulative net generation for Cycle 17 was 2840708.90 MWh at the end of August 1997. Cumulative net generation for Cycle 16 was 5418326.6 MWh.

Data Source: Station Generation Report Accountability: Chase Trend: None 25 l

1

, , Monthly Forced outage Rete .

+ Rolling 12 Month Awrage

_,_.1997 Fort calhoun Goal (1.4%)

50% .

45%.

40% .

35%.

30% +

25%..

I 20% .

15% +

A 10%. / ' '

6%. : : : : : [

0% * *

A * * * * * * *

l 96 Sep oct Nov Dec Jan Feb Mar Apr May Jurw July Aug

.J FORCED OUTAGE RATE The Forced Outage Rate (FOR) for the month of August 1997 was 0.0 %. The forced outage rate for the previous 12 months (September 1996 through August 1997) was 7.31%. The 1997 year-to-date FOR was 9.3% at the end of August 1997. This indicator needs increased management attention since it exceeds the FSS goal.

Energy Losses are described in the " Unit Capability Factor" indicator, page 2 of this report.

The 1997 Fort Calhoun Station year-end goal for this indicator is a maximum value of 1.4%.

Date Source: Monthly Operating Report Accountability: Chase Trend: None 26 l

. rm MonthlyunitCapacityFactor

. . .o. . . Year to-Oste unit Capacity Factor

+ thit Capacity Factor for C)cle 17

._,_1997 PCS Goal (96.00Yd 110 % ,

100 % .

- D -

i..-]....f}e..<l,"T"'":+.i:i

,,, z y -

.e..... ,

p -

60 %

60% .. &

Cycle 17 [y i g: h(, h E

40%. _

g ll [ } ,f 30%.

[.)

)I jf -

{j f( '

20% -

s ${ $U -

p$ $ $ $

b 10% + ij s.

f st ..

. J 0% 1_ fA N N 1

S Y $ I?

C-16 Sep Oct Nov Dec Jan Feb Mar Apr Msy June July Aug UNIT CAPACITY FACTOR l

This indicator shows the plant monthly Unit Capacity Factor, the Unit Capacity Factor for ;

the current fuel cycle, the year-to-date, and the 1997 OPPD Station goal.

Unit Capacity Factor = Not Electrical Enerav Generated iMWH)

Max. Dependable Capacity (MWe) X Gross Hours in the Reporting Period Cycle 16 Unit Capacity factor was 76.76%.

At the end of August 1997, the Cycle 17 Unit Capacity Factor was 81.45%. The Unit Capacity Factor for the last 36 months (September 1994 through August 1997) was 83.30. The 1997 Fort Calhoun annual goal for this indicator is 96.00%.

The year-to-date value is 89.20%.

Data Source: Monthly Operating Report Accountability: Chase Trend: None 27

, , MortNyEM .

.o Year 40.Dete Average MortNy EM

+ 12 Morth R$ng Average i

+ OPPD Gbal j 100 % . N.3% 96.1 % M% 99.1 % 97.5 % 97.5 %

85.5 %

, Tr r .-

92.8% l 90% , * '

* \' "

i

. ,_ - m_ - -m 80% - 68.7 % 1 70% . 5- -

l 60% +

50% - 45.7%

40% .

30% . 1996 RFO 20% .

10% - 4.9%

3.1%

0% ,U n __

Sep Oct Nov Dec Jan Feb Mar 4r May June July Aug

?

i i

EQUIVALENT AVAILABILITY FACTOR This indicator shows the plant monthly Equivalent Availability Factor (EAF), the year-to-date average monthly EAF, the 12 month rolling average, and the OPPD goal.

The EAF for August 1997 was 92.75 %. The 12 month rolling average (September 1996 through August 1997) was 73.07%. The equivalent availability factor for the past three years (Septermber 1994 through August 1997) was 82.58%.

Ths Fort Calhoun Station goal for this indicator is an EAF of 93.00%.

Data Source: Dietz/Mikkelsen (Managers / Source)

Accountability: Chase Trend: None l

s 28

, m Safety System Actuatione (INPO Definhlon)

+ FCS Goal (0)

+ Industry Upper 10 Percentile (0) 3 2-1 o o o o o o o o o o o o o O e : : : : : : : : : : :=4 96 Sep Oct Nov Dec Jan Feb Mar Apr May June July log UNPLANNED SAFETY SYSTEM ACTUATIONS -(INPO DEFINITION) l There were no WANO unplanned safety system actuations during the month of August 1997.

There were no WANO unplanned safety system actuations during 1996.

The 1997 Fort Calhoun goal for this indicator is 0.

Data Source: Monthly Operating Report & Plant Licensee Event Reports Accountability: Phelps Trend: None 29

m Safety System Actuati:ns (NRc Definitisn)

i i Fct Ocal(0)

+ Critical Hours 10 __ 1ses RFo - 800 g

700

- 600 4 6-- 500 l

- 400

i 4~~

, 300 2- + 200 ee - 100 0 '

0 s O N D J F M A M J J A UNPLANNED SAFETY SYSTEM ACTUATIONS -(NRC DEFINITION)

This indicator shows the number of Unplanned Safety System Actuations (SSAs), which includes the High and Low Pressure Safety injection Systems, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of SSAs includes actuations when major equipment is operated and when the logic systems for these safety systems are challenged.

There have been no unplanned safety system actuations in the last 12 months. The 1997 Fort Calhoun goal for this indicator is 0.

Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs) i Accountability: Phelps l Trend: Positive l

I 30

[g39 Gross Heat Rate

Year to.Dete Gross Heat Rate

.w Fort Calhoun Goal 14.75 1 14.25 . (*

6 13.75 , p 13.25 12.75 !

g 12.25 . ,

11.75 h e 11.25 7

, g q 1"5A g 3 g 5 5 3 8 0 8 3

" " 5 ,

10.25 - y E ci , ,

g "g E "g "

i ' '

-1 96 I I I l~i Sep oct Nov Dec Jan i'l il e R Feb Mar Apr May June July Aug l

l GROSS HEAT RATE This indicator shows the Gross Heat Rate (GHR) for the reporting month, the year-to-date GHR, the goals, and the year-end GHR for the previous three years.

The gross heat rate for Fort Calhoun Station was 10,314 BTUlkWh for the month of August 1997. The 1997 year-to4 ate Average GHR was 10,154 BTUlkWh at the end of the month.

The GHR varies with fluctuations in river water temperature. In general, the GHR improves during the winter months and degrades during the summer. This is because the gross heat rate is not normalized to the design river water temperature of 60 degrees Fahrenheit.

The 1997 Fort Calhoun year-end goal for the Average GHR indicator is 10,166 BTUIkWh.

Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Skiles Trend: Positive 31

4

+ ThermC) Output

+ Fort Calhoun 1496 MW Goal a Toch Spec 1600 MW Limit "i -

e: : : : ; - : :

2

: : : : ; - ; : : : ; =- : i :p e 1490 1400.

1470.

h j 14 0.

1450

.0 1430 4 1420 1 2 3 4 5 6 7 8 9 10111213141516171819202122232425262728293031 l DAILY THERMAL OUTPUT The thermal output graph displays the cially operating power level during August 1997, the 1500 thermal megawatt average technical specification limit, and the 1498 thermal megawatt Fort Calhoun goal. The station operated at a nominal 100% power until July 10, when the reactor power was reduced to 95% to facilitate scheduled Screen Wash Pump repairs. Repairs were completed and re: ctor power reached 100% on July 12, a d remained there through the end of the month.

Data Source: Guinn/Schawe (Manager / Source)

Accountability: Chase /Short Trend: None 32

4

+ Monthh Equipment RHt

+ Equipment PORti,000 Critical Hrs. (Rolling 12 Month interval)

+ Fort Calhoun Year End ooals (0.2) 2, 1.

1 5 h : b \ _d \b a" e_. . . . . .

I Sep oct Nov Dec [an Feb M a- Apr May June July Aug EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL HOURS The Equipment Forced Outage rate per 1,000 critical hours for the 12 months from September 1,1996, through August 31,1997, was 0.142. The year-to-date rate per 1,000 critical hours for the months from June 1,1997 through August 31,1997 was 0.187.

The equipment forced outage that occurred April 21,1997 was attributed to the rupture of a fourth stage extraction steam pipe. A second outage occurred on May 24 due to a weld crack which caused reactor power to be reduced to 10% while repairs were made on line.

The 1997 Fort Calnm,n year-end goal for this indicator is a maximum value of 0.20.

Data Source: Monthly Operating Report & Plant Licensee Event Reports (LERs)

Accountability: Chase /Phelps Trend: None 33

CHEMISTRY ACTION LEVELS EXCEEDED ten osys + Anrepe twn: pers pOPPD Limlit s.

2.s .

p .

1- . . . .

_/-

o,.

o!

i s

8 8 { [ i2 i ! l {

~ ~ ~

i4 i~

a

~ t CHEMISTRY ACTION LEVELS EXCEEDED - EVENT DAYS ,

1 The Chemistry Action Levels Exceeded indicator tracks the number of days in which chemistry parameters exceeded a corresponding action level for the reporting month, as well as a 12 month average of days an action levelis exceeded. The parameter action levels are delineated in Chemistry procedure CH-AD-0003, " Plant System Chemical Limits and Corrective Actions".

An action level is considered to have been exceeded for the purpose of this indicator, whenever the parameter exceeds the CH-AD-0003 action level for the current system mode, with the exception of the Steam Generators during Mode 1.

The Steam Generators are considered to have exceeded an action levelin Mode 1 when the plant power is greater than 30% and the power is changing less than 5% per day.

The number of event days can exceed the number of days in a month since each event is counted separately and there can be multiple events per day.

The 1997 Fort Calhoun goal for th% indicator is the 12-month average of two event days per month. There is no goal established for the number of event days per individual month.

Historical data is used to calculate the monthly average event days. The 12-month average was calculated by dividing the number of event days by the number of preceding months, until twelve months were reached.

There were no event days in August-Data Source: Chase /Hamilto ,(Manager / Source)

Accountability: Hamilton Trend: None 34

i i% Hours Out of Lint 13.00 + OFPD Goal (5%) -

190 ,

11.00 9.00 7.00 .

5.00 : : : : : : : : : : :

2.93 3.00 . _

1.21 1.08 1.00 - 0,00 0,00 0,00 0,00 0,00 0,00 -

0,00 0,00

-# 8 1 1 4 ! a a ! .l ti PRIMARY SYSTEM LITHlUM % HOURS OUT OF LIMIT The Primary System Lithium Percent Hours Out of Limit Indicator tracks the hours per month that the primary system lithium is out of specification.

The Primary System Lithium Percent Hours Out of Limit was 1.08% for the month of August 1997.

The 1997 Fort Calhoun Station monthly goal for this indicator is a maximum of 5%

hours out of limit.

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Hamilton Trend: None 35

COST Goal: Operate Fort Calhoun Station in a manner that cost effectively maintains nuclear generation as an economically viable contribution to OPPD's bottom line. Cost consciousness is exhibited at all levels of the organization.

36

_e_ Aciv.i . suoo.i ei.n 3 s0 3.s0 .

3.40 .

3.20 .

3.00 N

%--o-a Is0 n.40 . M

.ro .

2.00 -

ama saaa5gaaaaaaaaggggg k k k k k .I k i 5'l .I 4 $ k 8 k k CENTS PER KILOWATT HOUR July 1997 The purpose of this indicator is to quantify the economical operation of Fort Calhoun Station.

The Cents Per Kilowatt Hour indicator represents the budget and actual cents per kilowatt hour on a 12 month rolling average for the current year. The basis for the budget curve is the approved 1996 and 1997 revised budgets. The basis for the actual curve is the Financial and Operating Report.

The December 31 amounts are a'.J shown for the prior years 1992 through 1996, in addition, the report shows the plan amounts for the years 1998 through 2002 for reference. The basis for the dollars are the Nuclear t.ong Range Financial Plan and the 1997 Corporate Planning and Budget Review. The basis for the generation is provided by Nuclear Fuels. The 12-month rolling average unit price (period of June 1996 through July,1997) averaged above the budget due to 12 month rolling expenses exceeding the budget and the 12 month budgeted generation falling below budget. The 12 month rolling average (6/96 through 7/97) is 3.33 cents per kilowatt hour.

The year to-date average is trending in a negative direction. This information normally lags by month due to the short tum around required for processing.

Cents per KWH Jan Feb Mar Anr May Jun Jul Aua San Oct Nov Dec Budget Y T D 2.83 2.66 2.58 2.55 2.44 2.46 2.48 2.46 2.46 2.46 2.45 2.44 Actual Y T D 2.89 2.00 2.54 2.75 2.99 2.90 2.83 0.00 0.00 0.00 0.00 0.00 Data Source: Lounsberry/ Dent (Manager / Source)

Accountability: Lounsberry Trend: Needing increased Management Attention 37

i i i l l l i

l l

l DIVISION AND !

DEPARTMENT l PERFORMANCE i INDICATORS l i

l Goal: Achieve high standards at Fort Calhoun Station !

resulting in safe, reliable and cost effective power ;

! production. !

l l

l i

38

- . - _ . _ _ _ _ _ _ - . _ _ . _ _ _ _ . . . . . , _ . _ _ _ _ _ , ~ . _ . . _ , . _ _

m Corr:ctNo Maint: nance , , Pr:ventive M: Int:nanco Non Corrective / Plant Improvements Fort Calhoun Goal 80w 0 637 742 729 684 682 624 625 763 674 600 1 g i

400 N 200 a 1

0 .L - . _._ -_ + - __ . . _ + -

E Non Outage Maintenance Work Document Backlog Past Completion 0 Total Wh conpleted MADPRCHTY _-

48%

G, M f 4I. g b -

2D<. 0 1 N

56 5

Qh '

OL. 4-

- 52%

Rot / Rut / Rut / Rot / Rut / Not Conpleted 1 2 3 4 5 MAINTENANCE WORKLOAD BACKLOG This indicator shows the backlog of non-outage Maintenance Work Documents remaining open at the end of the reporting month. It also includes a breakdown by maintenance classification and priority. The 1997 goal for this indicator is 350 non-outage corrective maintenance MWDs. The current backlog of corrective MWDs is 352. To ensure that the MWD backlog is worked in a timely marmer, non outage maintenance completion goals have been established as follows:

Go.al l Priority 1 immediate Action 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

, Priority 2 Urger.t 5 days l Priority 3 Operational Concerns 21 days Priority 4 Routine Corrective 90 days Priority 5 Non Essential 180 days Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: Adverse SEP 36 39

Ratio of Prewntive to Total Maintenance 90%

90% - 82% B4% . ,

II !

('

80%~ -

74 %

g 70%

7 70% _

s% b k k ,. 62 % ,

50% - pj 7 lis , j 40%

7 ,, 7.] ,,. g 30 % i n y ;j i3 20%1 ( U ??s 10%. id 5 D 0% U' 1 N I' I A >

$ b b b k b 5 h $ h k $

w Preventive Maintenanc=ltems Overdue

+ rortcathounooal 3% + 2.60%

2.50 %

2% .

1% - .63% 0.56 % 0.56 %

.10%

0.25%

1

~

,% i ; j s e e a rs 1 8 a 1 4 2 1 1 1 j i I RATIO OF PREVENTIVE TO TOTAL MAINTENANCE PREVENTIVE MAINTENANCE ITEMS OVERDUE l

The top graph shows the ratio of completed non-outage preventive maintenance to total completed non-outage maintenance The ratio was 2.50% for the month of August 1997.

The lower graph shows the percentage of scheduled preventive maintenance items that are overdue. During August 1997,432 PM's out of 11 were completed.

The 1997 Fort Calhoun monthly goal for the percentage of preventive maintenance items overdue is a maximum of 0.5%,

Data Source: Chase / Johnson (Manager / Sources)

Accountability: Chase /Faulhaber Trend: None SEP 41 & 44 40

mN). Maintntnce inme comp %td

% % Identified as Repeat 700 'I'

, . 0%

m. ,,,

m ..n

~

. 4 0%

m .. m 300 , 3.g 173 7

m. 'V a

y W

y y F

/* ,

y

. 41 % *"

m. 9F

_ M_ e tt 4 7 il r,e .in

, 4 4 9 w e u a w , , ,

s ., o., n, o.. s. r ., u, a ,, u ,, u. u, a, (ma Rework as identified by Craft

%- Fort Calhoun Ocal(<3%)

1 3% , e : : : : : : '? : : e :

$ N R .'

l + l.8 % 4.8 % 88%

f '#

~

e. .

E

$ m . , ,, , , ,

..., a- be.' g ...,

Cop Oct Nov Dee Jan Feb Mar Apr May June July Aug PERCENTAGE OF TOTAL MWDs COMPLETED PER MONTH IDENTIFIED AS REWORK / REPEAT This graph indicates the percentage of total MWDs completed per month idenJfied as rework. Rework activities are identified by maintenance planning and craft.

This indicator is calculated from the 15th of September though the 15th of August 1997, due to the delay in closing open MWDs at the end of each month. The Fort Calhoun monthly goal for this indicator is <3% A detailed review is conducted of rework items each month to identify generic concems.

Data Source: Faulhaber/ Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: None 41

i iMonthly Dertime (On-Urm) ,

+ Y+T D Monthly Aworage (On Urw) ,

+ FortCalhoun"OnUne" Goal (10W 21A%

~

20.0% _

15.0%

9 9.8%

10.0% ._ : : : e : : : : , e :

6.0% .

4.5% # -

5.0% . 44%

0.0%

0.0% :

Jan Feb Mar Apr May Jun Jtd Aug Sep Oct Nov Dec d

MAINTENANCE OVERTIME

, The Maintenance Overtime Indicator monitors the ability to perform the desired maintenance activities with the allotted resources.

The percent of overtime hours with respect to normal hours was reported as 3.2% for the month of August 1997.

The 1997 Fort Calhoun monthly "on line" goal for this indcator is a maximum value of 10%.

Data Source: Chase / Johnson (Manager / Source)

Accountability: Chase /Faulhaber Trend: None 42

Hum:n Porfsrm:nco CRs (Maintsnanco) 20 -

18 --

16 --

14 --

12 --

a g 10 --

o 8 -

6-- 5 5 i t i i i i Feb Mar Apr May June July Aug PROCEDURAL NONCOMPLlANCE INCIDENTS (MAINTENANCE)

This indicator shows the number of Condition Reports relatea to procedural noncompliance incidents assigned to the Maintenance Department.

Data Source: Faulhaber/Borggraf (Manager / Source)

Accountability: Chase /Feulhaber Trend: None SEP 15,41 & 44 l

l l 43

1 e WhiCIO6$ .-x % RnPAUDDS' '

+ %Totaloos + Total % ooS Goat 1.*M .

12%s 10% : '

8% . ,

0% ,

43 l ,x x *

[x ^

N l

/- "

\x , -

'x 2%

0% N : : : 's : -

8 8 8 8 k k k u 5 a m B h $ h b k b b k $ k b $

1 IN-LINE CHEMISTRY INSTRUMENTS OUT-OF-SERVICE This indicator shows the percentage of hours the in-line chemistry system instruments are Inoperable for the reporting month. The chemistry systems involved in this indicator include the Secondary System and the Post Accident Sampling System (PASS). At the end of August 1997, the percentage of hours the in-line chemistry system instruments were inoperable was 4.53%. The following instrument (s) were out of service for the current month:

1. % PASS HOURS OUT OF SERVICE:

PASS IC was broken for 13 days, it is now fixed.

2. % NON-PASS HOURS OUT OF SERVICE:

AO-110 out of service. Various I&C calibrations in progress .

Data Source: Chase /Ostien (Manager / Source Accountability: Chase /Skiles Trond: None 44

i _.i Waste Produced Each Month (Kilograms) l

_,_. Fort Calhoun MontNy Average Goal (150 kilograms) l

+ Fedoral & State MontNy Umit (Max. of 1,000 kg) l 1000 : : :. : : : :. :. :.

900 1 800 !

700 g 600 2 5004 400 3001 200__

100 + .. g 0! ,

l ,

t m 3 o z j ,li t w

is a

< t.

z E

y it, <

F HAZARDOUS WASTE PRODUCED This indicator shows the total amount of Hazardous Waste Produced by the Fort Calhoun Station each month, the monthly average goal and th9 monthly average total for hazardous waste produced during the last 12 months. This hazardous waste consists of non-halogenated hazardous waste, halogenated hazardous waste, and other hazardous waste produced.

During the month of August 1997,0.0 kilograms of non-halogenated,0.0 kilograms of halogenated and 0.0 kilograms of other hazardous waste were produced.

Hazardous waste is counted based upon a full drum of waste.

The 1997 Fort Calhoun monthly average goal for hazardous waste produced is a maximum of 150 kilograms.

Data Source: Chase /Shubert (Manager / Source)

Accountability: Chase / Hamilton Trend: None 45

r -- ri Contaminated Radiation Controlled Arca

-. Fort Calhoun Goal ($%)

10%- : : : : : : :

9% -

m 8% - ;q a _ _ _

7% - ,

l' < M E *-

dU T 6% -

Y I,1 $,' f 5% + ,

'A A

( '

,u h fl; 4% -

hi .. ,

((3 .

p tl 2 21 i 3%

T

Eh rt '

l a5 v, .

1,+

m)

N N h iU 2% - --

! $ 'f s{iQg

@ci

_ 3

)e f,t Hj M 1% + ,

Si P ,

l h 4 i f VT R

.)d 7 0% '

M \

Sep Oct Nov Dec Mn Feb Mar Apr May June July Aug CONTAMINATED RADIATION CONTROLLED AREA This indicator shows t$ a percentage of the Radiologically Controlled Area that is contaminated based on the total square footage. The 1997 monthly non-outage goal was revised from a maximum 10% to 5.0% contaminated RCA in May 1997. This indicator has an Adverse Trend since it exceed the FCS goal.

At the end of August 1997, the percentage of the total square footage of the RCA that was contaminated was 7.9%.

Data Source: Chase / Williams (Manager / Source)

Accountability: Chase /Gebers Trend: Adverse SEP54 46

. : Pccr R:dlation Wcrk:r Pra:tices

-+--Fcrt Calh:un Crat (<15)

-*-Total PRWP for 1997 16 T

12 10 6

/

2 1 0

Jan Feb Mar Apr May June July Aug Sep oct Nov Dec RADIOLOGICAL WORK PRACTICES PROGRAM The Radiological Work Practices Program indicator shows the number of Poor Radiological Work Practices (PRWPs) which were identified during the reporting month.

The number of PRWPs which are identified each month should indirectly provide a means to qualitatively assess supervisor accountability for their woiKers' radiological performance.

This indicator needs increased management attention due to a 3 month increasing trend of poor radiation worker practices based on YTD.

During the month of August 1997, there was 2 PRWP identified.

There have been a total of 9 Poor Radiation Worker Practices in 1997.

The Fort Calhoun Station year-end goal for PRWPs is a maximum of 15.

Data Source: Chase / Hamilton (Manager / Source)

Accountability: Chase /Gebers Trend: Needing Increased Management Attention SEP52 47

O Documents Scheduled for Review .

g Documents Reviewedduringmonth g Documents Overdue 400 _. -

350 n _

~

300__ _

l 250 .

200 _

150__

100 I 50 .. i Oi M, E; E N l1 h: d 3 I I ! q

"

3 g B W = 2 h. t 8'

$ 2 o , u. 3 < z 4 y 4 1997 DOCUMENT REVIEW The Document Review indicator shows the number of completed, scheduled, and overdue (greater than 6 months past the scheduled due date) blennial reviews for the reporting month. The documents reviews are performed in-house and include Special Procedures, the Site Security Plan, Maintenance Procedures, Preventive Maintenance Procedures, and the Operating Manual.

During August 1997, there were 309 document reviews scheduled, while 63 reviews were completed. At the end of the month, there were 90 document reviews more than 6 months overdue. There were 6 new documents initiated during August 1997.

Data Source: Chase /Plath Accountability: Chase /Skites Trend: None SEP 46 48

i m Systom Follurea O Non System Failures ,

l 27

' 25 25 --

l

o -- 1919 15 o y Sep Oct Nov Dec Jan Feb Mar Apr M ay June July August f "

l LOGGABLE/ REPORTABLE INCIDENTS (SECURITY) i l The Loggable/ Reportable Incidents (Security) Indicator is depicted in the above graphics !

! display. The graph depicts the total number of loggable/ reportable non-system failures and system failures which occurred during the reporting month.

During the month of August 1997, there were 11 loggable/ reportable incidents identified.

2 This was a 35% decrease from the previous reporting period. System failures accounted

! for 55% of the total failures. Three (3) of the six (6) failures were environmental. Three l Security Force error events, and two lost / unattended security badges, were the

nonsystems failures that increased duiing the reporting month.

This indicator provides information on security performance for Safety Enhancement Program (SEP) Item No. 58.

Data Source: Sefick/Woemer (Manager / Source)

Accountability: Sefick i Trend: None SEP58 j 49 l

i l

C~'"") Tempstary Ocdificatins >1 cycle aid (RFO t, quired far romsval) m Tempstary Ocdificat'she >s m2aths old (Rem 3vable sa lise) ,

- - - Fort eclhsva Osals f2r >1 cycle sad as m2nths eld 3 8 3.

~

s s s s n. s s

- ** ~* m o = = . . m. . . . .m . .

5 b $ b b ? 5 5 $ k k $

TEMPORARY MODIFICATIONS This indicator provides '.aformation on the number of Temporary Modifications (TMs) greater than one fuel cycle old requiring a refueling outage (RFO) for removal and the number of temporary modifications removable on-line that are greater than six months old.

The 1997 Fort Calhoun monthly goals for this indicator are zero.

There are currently two (2) temporary modifications that are greater than one-fuel cycle old requiring an outage for removal. TM 96-014, Reactor Coolant Gas Vent Line Pressure High Alarm, was installed April 22,1996. Repairs for this TM were completed during the 1996 RFO, but the reactor coolant gas vent line pressure is si high. MR-FC 011 was initiated to solve this problem and currently DEN is planning the modification. TM 96-018, Equipment Drain Header Soft Rubber Patch, was installed June 16,1996. MWO 963468 is currently scheduled for the 1998 RFO.

At the end of August 1997, there was one (1) TM installed that was greater than six months old that could be removed on-line. TM 96-039, Railroad Siding / Corridor 26 Door, was installed November 1,1996. A gel-35 EAR will close this TM. EAR 97-219 requires e System Engineering review and approval.

At the end of August 1997, there was a total of 12 TMs installed in the Fort Calhoun Station. Nine (9) of the 12 installed TMs require an outage for removal and 3 are removable on-line, in 1997, a total of 16 TMs hvo been installed. At the end of August 1997, there were two (2) procedural or maintenance configuration alterations (PMCAs) (a special classification of TM) installed in the Fort Calhoun Station using PRC approved procedures. These PMCAs are controlled by Standing Order O-25.

Data Source: Phelps/ Frank (Manager / Source)

Accountability: Phelps/ Core Trend: None SEP 62 & 71 50

i i Total Modification Packages open

-- Fort Calhoun Year End Goal (68) ao . 7, E ,, E E E

~

75 ,

70 + 3 e . : : : : : : : : : :

65 4- ,

1 96 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec OUTSTANDING MODIFICATIONS This indicator shows the total number of Outstanding Modifications (excluding outstanding modifications which are crocosed to be cancelled).

Reporting Categorv '9.4 .95 '93 '91 E 2 Month Form FC-1133 Backlog /In Progress 0 0 0 1 0 0 1 Mod. Requests Being Reviewed 0 0 0 0 0 7 7 Design Engr. Backlog /In Progress 0 0 0 0 14 3 17 Construction Backlog /In Progress 3 1 5 7 3 0 19 Design Engr. Update Backlog /in Progress 4. _12 .11 1 _Q _Q 28 Totals 7 13 16 9 17 10 72 (outage + onune) (3+4) (5+s) (13+3) (2+7) (15+2) (7+3)

At the end of August 1997,25 modification requests have been issued this year and 7 modification requests have been cancelled. The Nuclear Projects Review Committee (NPRC) has conducted 64 backlog modification request reviews this year. The Nuclear Projects Committee (NPC) has completed 22 backlog modification request reviews this year.

The 1997 year-end Fort Calhoun goal for this indicator is a maximum of 68 outstanding modifications.

Data Source: Jaworski/ Walling (Manager / Source)

Lounsberry/Belek (Manager / Source)

Accountability: Lounsberry/Jaworski Trend: Needing increased Management Attention 51

... 2 ,,

sia. a...,n. ..n..,u.en.e.. .w.ia eo...u.

e SE a DEN e 38 84 28 l 20 . 17 17~ 17 l o 7 r -

r

! u t, . i i i i l* ,

, l [5 li ,' .' .$ - fi

' '

I June J u ly Aug June J u ly Aug June July Aug June J u ly Aug 0 3 M onths 3 6 M onths 412 M onth s mit M onths O Engineering Response c) Closeout (sE)

$7 20 I , o 3 5 6 10 9 3 g 3 q g 1 o o I I * '

OI I Priority 0 Priority 1 Priority 2 Priority 3 Priority 4 PriorityS Priority 6 44 Ove rdue cia aut . , cA... on a ,aa, -

12% Schedule 86.0%

eas

Response

2

-12 overdue 125% Close outs s.0%

ENGINEERING ASSISTANCE REQUEST FREAKDOWN This indicator shows a breakdown of the number of EARS assigned to Design Eng!neering and System Engineering. The 1997 year-end goal for this indicator is a maximum of 140 outstanding EARS.

The Total EAR breakdown is as follows:

EARS opened during the month 11 EARS closed during the month 1Q Total EARS open at the end of the month 137 Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Phelps/Jaworski Trend: None SEP 62 52

48 325

$ UT

qgg EN e M 0nths 0 3 M onths as% 0 N N * '

54 3 s Months co r.

s[e IGN 5 l ATUS - OVERAu. BACKLOG O Backlogged O Receiveci g Completed n,3 M onth s 150 .113 115 110 115 its 119 4 ,,

26 5 6 M o nth s 50 . 00 - - -

u , , ,n ,

50 - Mar Apr May Junc July Aug l DESIGN ENGINEERING ]

250} 1 s u o n th.

T s ts%

150y e s u onths s.

79 sy 90 85 7%

100 J. 76 81

.su o nthe g ?

Mar Apr May June July Aug 1

[SYSTEtJENGlNEERlRG 300 225 33 250 211 221 211 217 206 s s uoains 3 200 81%

s-s Months L,501 5 310 9 12 00 125 36 as uontne 01 ~ - ., a4%

Mar Apr May June July Aug

[PROCLREFENT/CONSTUCTION 2s0 _ s ,

Mo hs Mc th s 82 00 M onths Wr Apr by June July Aug

!_DRAFRNG/ CLOSEOUT __ __j ENGINEERING CHANGE NOTICE STATUS Data Source: Jaworski/Livingston (Manager / Source)

Accountability: Jaworski/Phelps Trend: None SEP62 53

. u, ,, ..

.e ,,,i

,,,..... ,,i....

M , G ,c ,,,, hg 4 v - a n J see f w ses Total Open ECNs a 463 , ,,, 87

,s Total Open ECNs a 463

...i.,

j y.g:gg.i";j{!l.F.';EE.=::=-

faa

, e, i

. '.' 22

.4 ei

]ivis2 ,,,,,333 ney.

*'t.. 4 s ' .. eW.b. "' '"

I

253 253 114 253 24, 37 47 87 I $

} 14 R W 5&6 g 200 4 15%

5 28 %

4 4 2 Mar 47 Agr47 May47 Jur>47 Jul47 W 343 Sdatitute Repia nant itemECNs Open R. ray s&4 57 %

et 3 78 77 78 76 gy DDN g 7l; a '

h '2 7

,, aany 3&s I,,

< //f.^M*

i .,

s. i. ,,

4=(

i E 10 g g, to

" a le . e ,m 2-.

Mar Apr May June July Aug / -v.c. , M, , ..

Docununt Change ECNs Open ENGINEERING CHANGE NOTICES OPEN Data Source: Jaworski/Livingston (Manager Source)

Accountability: Phelps/Jaworski Trend: None SEP 62 54

O Admini:trativo Centrcl Pr:bi m C3 Lic:ncod Opor:t:r Errer g Other Personnel Error g Maintenance Problem a Design /Constructionlinstallation/ Fabrication Problem 3 Misc.

3 -- .

2-1-- . . . . . . . .

0 ,

, y

$ $ b $ $ k $ $ 5 $ k $

LICENSEE EVENT REPORT (LER) ROOT CAUSE BREAKDOWN This indicator shows the LERs by event date broken down by Root Cause Code for each of the past twelve months from August 1,1996, through July 31,1997. To be consistent

with the Preventable / Personnel Error LERs indicator, this indicator is reported by the LER event date, as opposed to the LER report date.

The cause codes are intended to identify possibla programmatic deficiencies. For detailed descriptions of these codes, see the " Performance Indicator Definitions" section of this report.

NOTE: Due to the way LERs are tracked & reported, this indicator is ane-month behind.

There was One event in July 1997 that resulted in a LER.

Data Source: Tills /Cavanaugh (Manager / Source)

Accountability: Chase Trend: None 1

55

O Total R: qualification Tr;ining Hours l

0 simulator Training Hours s Non-Requalification Training Hours O Number of Exam Fallures 32.5 32 l

31 31 31 30 . - ~

j 25 .

22 f

20 .

l 5.5 1 15 .- 4 4 14 2

10 ..

b 9 9 8

j 5 -

1 1 1 0 0 0 0 0 0 0 -- + i ; .

+ - !

Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle Cycle 96-2 96-3 96 4 96 7 97 1 97-2 97 3 97 4 97 5 LICENSED OPERATOR REQUALIFICATION TRAINING This indicator provides information on the total number of hours of training given to each crew during each cycle. The simulator training hours shown on the graph are a subset of the total training hours. Non-Requalification Training Hours are used for AOP/EOP verification & validation, INPO commitments, GET, Fire Brigade, Safety Meetings, and Division Manager lunches.

Exam failures are defined as failures in the written, simuiator, and Job Performance Measures (JPMs) segments of the Licensed Operator Requalification Training.

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 56

O sRO Exams Administered O sRO Exams Passed O RO Exams AdminHered a RO Exams Passed 10 . -

77 77 77 77 m

5.

0000 00 00 00 00 0000 0000 0000 Jan Feb Mar Apr May Jun Jul Aug sep Oct Nov Dec LICENSE CANDIDATE EXAMS - 1997 This indicator shows the number of Senior Reactor Operator (SRO) and Reactor Operator (RO) quizzes and exams taken and passed each month. These intemally administered quizzes and exams are used to plot the SRO and RO candidates' monthly progress.

During the month of August 1997, there were no (SRO) or (RO) training classes in session.

Data Source: Conner /Guliani(Manager / Source)

Accountability: Conner /Guliani Trend: None SEP 68 57 1

m Rea$y to cose

. ,cosed i l

% TotalCRs

+ open 3000 ;

1 i

2500 2000 1soo.

1000 a . .

W' soo .

0 8 ~

8 8 8 8 8 8 8 a k k 3 e a a I4 4 IA$ 5 $4 !$ i I4 4 I i

i CONDITION REPORTS BY LEVEL This indicator shows the total number of Cor dition Reports which are Closed, Ready to Close, Open and the Total Number of Condithn Reports fo date.

Level 1 Level 2 Level 3 Livel 4 Level 5 Level 6 Total 4

Open 24 19 122 842 43 182 1244 j Closed 15 7 113 1100 462 215 1992 265 Condition Reports are classified as READY to CLOSE.

Data Source: Tesar/Burggraf (Manager / Source)

Accountability: Andrews/Gambhir Trend: None 58

a Total Outage MWDs O MWDs Ready to Work 1200.

Engineering Parts 1000. -

1% 5%

ECNs 800 -

,[ [ ~ 11 %

~

575 00 ~ 380

_ IN REVIEW 200 158

- M 47%

0 Apr97 Wr97 Jun-97 Jul-07 Aug-97 MWD PLANNING STATUS (CYCLE 18 REFUELING OUTAGE)

This indicator shows the total number of Maintenance Work Requests (MWRs) and Maintenance Work Documents (MWDs) that have been approved for inclusion in the Cycle 18 Refueling Outage. This graph indicates:

Parts Holds - Planning Complete, Awaiting Parts System Engineering Holds - Awaiting System Engineering Input to Planning Planner Holds - Maintenance Planner has not completed planning the work package.

ECN Hold - Awaiting Substitute Replacement items ECN from DEN.

D ta Source: Chase / Johnson (Manager / Source)

Accountability: Chase / Herman Tr:nd: None SEP 31 59

l g LastMonth a ThisMonth O Next Month I

f 120-110-100..

90 _

80 _.

! 3 70 ._

2

&s0. 3 O E" E" %% 40 50 . , .

% 0% g 40 - E 8 8 88 A h

x. * #

20 h

! 10 . M l

l 0 4 ) -

s - e o i g . v-l 2 i ? 8 = 2? .% is i e aa g a 5 .: te a gs , e a sE i. a

! E el 8 ) -

!" .d ?t l !" i i U $$

l $ 5 i SPECIAL SERVICES ENGINEERING DEPARTMENT

! 1998 OUTAGE PROJECTS STATUS REPORT l

i Data Source: Phelps/Swearngin (Manager / Source) li Accountability: Phelps/Boughter Trend: None SEP 31 5

4 60 i

4 i , ,- - , . ._ _ - - - -

7/30/97 .

....:....... j 6/30/97 .

$/31/97 .

5/1/97 .

4/1/97 .

, AcOMNte l a Target FHC Date 7,

1/31/97 .

1/1/97 i lilillill!!!

PROGRESS OF 1998 REFUELING OUTAGE MODIFICATIONS CYCLE 18 This indicator shows the status of Modifications approved for installation during the Cycle 18 Refueling Outage (March 1998).

The goal for this indicator is to have all modification packages which were identified prior to March 20,1997, PRC approved by September 15,1997.

August 1997 Modifications added: 0 Deleted = 0 -

Data Source: JaworskiAValling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP31 61 i

. Aid RCEde a Tagt FFCDde .

E 12f17197I 1Cr&97. $'

!=

2 97 + R ,g -

2 97 I h SW31-4'1W7 -

22n7 vwt .

9E8

%ER E$$

ww PROGRESS OF CYCLE 18 OUTAGE MODS AND ECN'S ADDED TO '98 REFUELING OUTAGE AFTER FREEZE DATE This indicator will show the status of Modifications and ECN's approved for installation

- during the Cycle 18 Refueling Outage. The goal for this indicator is to have all modification packages PRC approved by their target date.

August 1997 Modifications /ECN's Added = 0 Deleted = 0 Data Source: Jaworski/ Wailing (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP33 62

No 1997 On Line Modifications Currently Approved PROGRESS OF 1997 ON-LINE MODIFICATION PLANNING This indicator shows the status of modifications approved or in review for approval for on-line installation during 1997.

The goal for this indicator is to have all modification packages PRC approved by their scheduled date.

August 1997 Modifications Added: 0 Deleted: 0 Data Source: Jaworski/ Walling (Manager / Source)

Accountability: Gambhir/Jaworski Trend: None SEP31 63 i

i

+

4 ACTION PLANS O

64

ACTION PLANS This section lists action plans that have been developed for the performance indicators cited as Adverse Trends during tne month preceding this report. Also included are Action Plans for indicators that have been cited in the preceding month's report as Needing increased Management Attention for three (3) consecutive months.

In accordance with Revision 5 of NOD-QP-37, the following performance indicators would require action plans based on three (3) consecutive months of performance cited as "Needing increased Management Attention":

. Maintenance Workload Backlogs (page 39)

A Work Managemer t System improvement project is currently in progress. The purpose of this project is to stream line the maintenance process at Fort Calhoun Station. This wil'. significantly -improve our " WRENCH TIME" by removing inefficiencies and ietated hurdles that prevent work from being accomplished in a timely manner, in addition, it is expected that schedule compliance will also increase and our maintenance backlog will decrease. This project is scheduled to be fully implemented by July 1997.

65

I PERFORMANCE INDICATOR DEFINITIONS AUXILIARY FEEDWATER SYSTEM SAFETY SYSTEM PERFORMANCE CLEAN CONTROLLED AREA CONTAMINATIONS 11,000 DIslNTEGRATIONS/ MINUTE PER PROBE AREA The sum of the known (planned and unplanned) unavailable hours and the estimated unavailable hours for the auxthary The personnel contaminaten events in the clean controlled feedwater system for the reporting penod divided by the enbcal area. This indicator tracks personnel performance for SEP hours for the reporting penod mulupied by the number of trains #15 & 54.

In the auxiliary feedwater system.

CONTAMINATED RADIATION CONTROLLED AREA COLLECTIVE RADIATION EXPOSURE The percentage of the Radiaton Controlled Area, which Collective radiaton exposure is the total extemal whole body includes the auxihary building, the radweste building, and dose received by all on-site personnel (including contractors areas of the C/RP building, that is contaminated based on the end visitors) during a trne period, as measured by the total square footage. This indicator tracks performance for thermoluminescent dosimeter (TLD). Collective radiabon SEP #54, exposure is reported in units of person-rom. This indicator tracks radiological work performance for SEP #54. DAILY THERMAL OUTPUT COMPONENT FAILURE ANALYSIS REPORT (CFAR) This indicator shows the deity core thermal output as

SUMMARY

measured from computer point XC105 (in thermal megawatts).

The 1500 MW Tech Spec hmit, ant' the unmet porbon of the 4

lhe summary of lNPO categonos for Fort Calhoun Staton with 1495 MW FCS daily goal for the reporting month are also significantly higher (1.645 standard deviatens) failure rates shown.

than the rest of the industry for an eighteen month bme period.

, Failures are reported as component (i.e., pumps, motors, main DIESEL GENERATOR RELLABILITY (25 Demands) steam stop valves, control element motors, etc.) categones.

This indicator shows the number of failures occurring for each Failure Cause Categories are: emergency diesel generator during the last 25 start demands and the last 25 load-run demands.

Age / Normal Use thought to be the consequence of expected wear, aging, end-of-hfe, or normal use . DISABLING INJURY /lLLNESS FREQUENCY RATE (LOSS TIME ACCIDENT RATE)

Manufacturing Defect. a failure attributable to inadequate assembly or initial quahty of the responsible component or This indicator is defined as the number of accidents for a!!

system. utihty personnel permanently assigned to the station, involving days away from work per 200,000 man-hours worked (100 Engineering / Design a failure attributable to the man years). This does not include contractor personnel This inadequate design of the responsible www.r.t or system. Indicator tracks personnel performance for SEP #25,26 & 27.

Other Devices a failure attnbutable to a failure or DOCUMENT REVIEW (BIENNIAL) misoperation of another component or system, including associated devices. The Document Revew Indicator shows the number of documents rennewed, the number of documents scheduled for MaintenancelAction . resulting from improper review, and the number of document reviews that are overdue maintenance, lack of maintenance, or personnel errors that for the reporting month. A document review is considered occur during maintenance activitieson the component., overdue if the review is not complete within six months of the assigned due date. This indecator tracks performance for SEP Testing Action . resultmg from irnproper testing or #46.

personnel errors that occur dunng testmg activites.

EMERGENCY AC POWER SYSTEM SAFETY SYSTEM Initial Installation Error . caused by knproper initial PERFORMANCE installation of equipment The sum of the known (planned and unplanned) unavailable CENTS PER KILOWATT HOUR and the ratimated unavailable hours for the emergency AC power system for the reporting period divided by the number The purpose of this indicator is to quantify the economical of hours in the reporting period multiplied by the number of 1 operation of Fort Calhoun Station. The cents per kilowatt trams in the emergency AC power system.

hour indicator represents the budget and actual cents per kilowatt hour on a twelve-month average for the current year. The basis for the budget curve is the approved yearly budget. The basis for the actual curve is the Financial and Operating Report.

66

PERFORMANCE INDICATOR DEFINITIONS EMERGENCY DIESEL GENERATOR UNIT RELIABILITY minutes.

E) A failure to start because a portion of the starting system The indcator shows the rurcer of f& rte that were reported dunng the was disabled for test purpose,if followed by a successful last 20, 60, and 100 emergency desel generator demands at the Fort start with the starting system in its normal alignrnent.

Calhoun Statiert Also shown are tigger values whch correlate to a hsgh level of conndence that a unit desel generators have obtained a

"'"****#"**** Each emergency generator failure that results in the generator n being declared Inoperable should be counted as one demand and one failure. Exploratory tests during corrective

1) Number of Start Demands: All valid and inadvertent maintenance and the successful test that follows repair to start demands, including all start-only demands and all verify operability should not be counted as dernands or failures start demands that are followed by load-run demands, when the EDG has not been declared operable again.

whether by automatic or manual initiation. A start-onfy demand is a demand in whe the emergency generator EMERGENCY DIESEL GENERATOR UNRELIABILITY is started, but no attempt la made to load the generator.

This indicator measures the total unreliability of emergency

3) Number of Start Failures: Any failure within the diesel generators. In general, unreliability is the ratio of emergency generator system that prevents the generator unsuccessful operations (starts or load-runs) to the number of from achieving specified frequency and voltage is vahd demands. Total unreliability is a combination of start classified as a vahd start failure. This includes any unreliability and load 4un unrehability.

condition identrfied in the course of maintenance inspections (with the emergency generator in standby ENGINEERING ASSISTANCE REQUEST (EAR) rnode) that definitely would have resulted in a start failure BREAKDOWN if a demand had occurred.

This indicator shows a breakdown, by age and priority of the

3) Number of Load-Run Demands: For a valid load-run EAR, of the number of EARS assigned to Design Engineering demand to be counted, the load-run attempt must meet Nuclear and System Engineenng. This indicator tracks one or more of the following enteria: performance for SEP #62.

A) A load-run of any duration that results from a real ENGINEERING CHANGE NOTICE (ECN) STATUS automatic or manualinitiation.

The number of ECNs that were opened, ECNs that were B) A load 4un test to satisfy the plant's load and completed, and open beklog ECNs awaiting completion by duration as stated in each test's specifications. DEN for the reporting month. This indicator tracks performance for SEP #62.

C) Other special tests in which the emergency generator is expected to be operated for at least one ENGINEERING CHANGE NOTICES OPEN hour while loaded with at least 50% of its cesign load. This indicator breaks down the number of Engineenng Change Notices (ECNs) that are assigned to Design Engineenng

4) Number of Load-Run Failures: A load 4un failure Nuclear (DEN), System Engineenng, and Maintenance. The should be counted for any reason in which the graphs provide data on ECN Facihty Changes open, ECN emergency generator does not pick up load and run as Substitute Replacement items open, and ECN Document predicted. Failures are counted dunng any valid load 4un Changes open. This indicator tracks performance for SEP demands. #62.

9) Exceptions: Unsuccessful attempts to start or load-run EQUIPMENT FORCED OUTAGES PER 1,000 CRITICAL should not be counted as valid demands or failures when HOURS they can be attributed to any of the following:

Equipment forced outages per 1,000 critical hours is the A) Spurious tnps that would be bypassed in the event inverse of the mean time between forced outages caused by of an emergency. equipment fai!ures. The mean time is equal to the number of hours the reactor is critical in a penod (1,000 hours0 days 0 hours 0 weeks 0 months ) divided by B) Malfunction of equipment that is not required dunng the number of forced outages caused by equipment failures in an emergency. that penod.

C) Intentional termination of a test because of EQUIVALENT AVAILABILITY FACTOR abnormal conoitsons that would not have resulted in major diesel generator damage or repair. This indicator is defined as the ratio of gross available generation to gross maximum generation, expressed as a D) Malfunctions or operating errors which would not percentage. Available generation is the energy that can be have prevented the emergency generator from produced if the unit is operated at the maximum power level being restarted and brought to load within a few permitted by equipment and regulatory limitations. Maximum generation is the energy that can be produced by a unit in a 67

- - . . . ~ .-- _ - _ . ~ , .-- ~ . ~ . - . - ~

O PERFORMANCE INDICATOR DEFINITIONS gNon period if operated continuously at maximum capacity. This indicator is defined as the number of accidents per 200,000 man-hours worked for all utility personnel permanentty assigned to the station that resuR in any of the following:

FORCED OUTAGE RATE 1) One or more days of restrided work (excluding the day of the accident);

2 This indicator is denned as the percentage of time that the unit 2) One or more days away from work (excluding the day of was unavailable due to forced events compared to the time the accident); and planned for electrical generation. Forced events are failures 3) Fatalibes.

or other unplanned condibons that require removing the unn from service before the end of the next weekend. Forced Contractor personnel are not included for this indicator, events include start up failures and events initiated while the unit is in reserve shutdown (i.e., the unit is available but not in IN LINE CHEMISTRY INSTRUMENTS OUT OF SERV)CE service..

4 Total number of in-line chemistry instruments that are out-of-FUEL RELIABILITY INDICATOR service in the Secondary System and the Post Accident This indicator is denned as the steady-state pnmary coolant l-i 131 actkity, corrected for the tramp uranium contribution and LICENSE CANDIDATE EXAMS normahzed to a common purification rate. Tramp uranium is fuel which has been deposited on reactor core intemals from This indicator shows the number of SRO and/or RO quizzes

previous defective fuel or is present on the surface of fuel and exams that are administered and passed each month.

elements from the manufacturing process. Steady state is This indicator tracks training performance for SEP #68.

def%ed as conhnuous operation for at least three days at a power level that does not vary more than + or -5%. Plants LICENSED OPERATOR REQUALIFICATION TRAINING should collect data for this indacator at a power level above 85%, when possible. Plants that did not operate at steady- The total number of hours of trasning given to each crew during state power above 85% should colied data for this indicator at each cycle. Also provided are the simulator training hours the highest steady-state power level attained dunng the month. (which are a subset of the total training hours), the number of non-REOUALIFICATION training hours and the number of

. The density correchon factoris the ratio of the specific volume exam failures. This indicator tracks training performance for of coolant at the RCS operstmg temperature (540 degrees F,, SEP # 68.

Vf = 0.02146) divided by the specific volume of coolant at normal letdown temperature (120' F at outlet of the letdown LICENSEE EVENT REPORT (LER) ROOT CAUSE cooling heat exchanger, Vf = 0.016204), which results in a BREAKDOWN density correction factor for FCS equal to 1,32.

This indicator shows the number and root cause code for GROSS HEAT RATE Licensee Event Reports. The root cause codes are as follows:

Gross heat rate is defined as the ratio of total thermal energy 1) Administrative Control Problem - Management and in Bntish Thermal UrJts (BTU) produced by the reactor to the supervisory deficiencies that affect plant programs or total gross electrical energy produced by the generator in activities (i.e., poor planning, breakdown or lack of kilowatt-hours (KWH). adequate management or supervisory control, incorrect procedures, etc).

HAZARDOUS WASTE PRODUCED

2) Licensed Operator Error - This cause code captures The total amount (in Kilograms) of non-halogenated hazardor errors of omission / commission by licensed reactor waste, halogenated hazardous waste, and other hazardou. operators during piant activities.

waste produced by FCS each month.

3) Other Personnel Error Errors of omission / commission HIGH PRESSURE SAFETY INJECTION SYSTEM SAFETY committed by non licensed personnel involved in plant SYSTEM PERFORMANCE activrties.

L The sum of the known (planned and unplanned) unavailable 4) Maintenance Problem -The intent of this cause code is hours and the estrnated unavailable hours for the high to capture the full range of problems which can be pressure safety injection system for the reporting period attributed in any way to programmatic deficiencies in the divided by the critical hours for the reporting period multiplied maentenance functional organization. Activities included by the number of trains in the high pressure safety injection in this category are maintenance, testing, surveillance, system. calibration and radiation protect:on.

INDUSTRIAL SAFETY ACCIDENT RATE INPO 5) Design / Construction /InstallatiorVFabrication Problem

- This cause code covers a full range of programmatic 68

o PERFORMANCE INDICATOR DEFINITIONS deficiencies in the areas of design, construction, installation, Plant improvement - Nonorrective maintenance and and fabncation (i e., loss of control power due to underrated plant improvements.

fuse, equiptrent not quahfed for the environment, etc.),

This indicator tracks maintenance performance for SEP #36.

6) Equipment Failures (Electronic Piece-Parts or Environmental-Related Faltures).This code is used for MAXIMUM INDIVIDUAL RADIATION EXPOSURE spurious failures of electronic pece-parts and failures due to meteorological conditions such as hghtning, ice, high The total maximum amount of radiation received by an winds, etc. Generally, it includes spunous or one-time individual person working at FCS on a monthly, quarterty, and failures. Electric components included in this category annual basis.

are circuit cards, rectifers, bistables, fuses, capacdors, diodes, resistors, etc. MWO PLANNING STATUS (CYCLE 17 REFUELING OUTAGE)

LOGGABLE/ REPORTABLE INCIDENTS (SECURITY)

The total number of Maintenance Work Orders that have been The total number of security incidents for the reporting month approved for inclusion in the Cycle 17 Refuehng Outage and depicted in two graphs. This indicator tracks securdy the number that are ready to work (parts staged, planning performance for SEP #58. complete, and all other paperwork ready for field use). Also included is the number of MWOs that have been engineenng MAINTENANCE OVERTIME holds (ECNs, procedures and other miscellaneous engineenng holds), parts hold, (parts staged, not yet inspected, parts not The percent of overtime hours compared to normal hours for yet amved) and planning hold 00b scope not yei completed).

maintenance. This includes OPPD personnel as well as Maintenance Work Requests (MWRs) are also shown that contract personnel. have been identified for the Cycle 17 Refueling Outage and have not yet been converted to MWOs.

MAINTENANCE WORKLOAD BACKLOGS NUMBER OF CONTROL ROOM EQUIPMENT This indicator shows the backlog of non-outage Maintenance DEFICIENCIES Work Orders remaining open at the end of the reporting month.

Maintenance classifications are defined as follows: A control room equipment deficiency (CRD) is defined as any component which is operated or controlled from the Control Corrective Repair and restoration of equipment or Room, provides indication or alarm to the Control Room, components that have failed of are malfunctioning and are provides testing capabildies from the Control Room, provides not perfomung their intended function. automatic actions from or to the Control Room, or provides a passive function for the Control Room and has been identified Preventive . Actions taken to maintain a piece of equipment as deficient, i.e., does not perform under all conditions as within design operating conditions, prevent equipment designed. This definition also apphes to the Altemate failure, and extend its hfe and are performed pnor to Shutdown Panets Al-17g, Al-185, and Al-212.

equipment failuro.

A plant component which is deficient or inoperable is Non-Corrective / Plant improvements . Maintenance considered an " Operator Work Around (OWA) Item" If some actrvities performed to implement station improvements or other action is required by an operator to compensate for the to repair non-piant equipment. condition of the component. Some examples of OWAs are:

Maintenance Work Priorities are defined as- 1) The control roorn level indicator does not work but a local sight glass can be read by an Operator out in the plant, Emergency . Conditions which significantfy degrade station safety or availabildy. 2) A defcent pump cannot be repaired because replacement parts require a long lead time for immediate Action - Equipment deficiencies which purchase /dehvery, thus requinng the redundant pump to significantly degrade station reliabihty. Potential for unit be operated continuously; shutdown or power reduction.

3) Special actions are required by an Operator because of Operations Concern Equipment deficiencies which hinder equipment design problems. These actions may be station operation. desenbed in Operations Memorandums, Operator Notes, or may require changes to Operating Procedures; Essential Routine corrective maintenance on essential station systems and equipment. 4) Deficient plant equipment that is required to be used dunng Emergency Operating Procedures or Abnormal Non-Essential . Routine corrective maintenance on non- Operating Procedures; essential station systems and equipment.

5) System indication that provides entical information during 69

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l PERFORMANCE INDICATOR DEFINITIONS normal or abnormal operatens l The above rnentioned outstanding modificatons do not include l modifcations which are proposed for cancellaton.

OVERALL PROJECT STATUS (REFUELING OUTAGE) l l

This indcator shows thw status of the projects which are in the '

NUMBER OF MISSED SURVEILLANCE TESTS RESULTING scope of the Refueling Outage.

IN LICENSEE EVENT REPORTS l PERCENTAGE OF TOTAL MWOs COMPLETED PER The number of Surveillance Tests (STs) that result in Licensee MOMTH IDENTIFIED AS REWORK l Event Reports (LERs) during the reporting month. This l

indicator tracks missed STs for SEP 860 & 61. The percentage of total MWOs completed per month identified l OPEN INCIDENT REPORTS as rework. Rework activites are identified by maintenance planning and craft Rework is: Any additonal vverk required t This indcator displays the total number of open incident to correct deficencies discovered during a failed Post Reports (irs), the number of irs that are greater than six Maintenance Test to ensure the component / system passes months old and the number of open significant irs. subsequent Post Maintenance Test.

PERCENT OF COMPLETED SCHEDULED MAINTENANCE OUTSTANDING MODIFICATIONS ACTIVITIES The number of Modification Requests (MRs) in any state The percent of the number of comnieted maintenance between the issuance of a Modification Number and the activites as compared to tM number of scheduled completion of the drawing rpdate. maintenance activites each month. This perantage is shown for all maintenance crafts. Also shown are the number of

1) Form FC-1133 Backlog /In Progress. This number emergent MWOs. Maintenance activites include MWRs, represents modification requests that have not been plant MWOs, STs PMOs, calibrations, and other miscellaneous approved during the reporting month. actmtes. This indicator tracks Maintenance performance for SEP #33,

2) Modification Requests Being Reviewed. This category includes: PERFORMANCE INDICATOR INDEX A) Modification Requests that are not yet reviewed. Dis indcator hdex is calculated from a weighted combination of eleven performance indcator values, which include the B) Modification Requests being reviewed by the following: Unit Capability Factor, Unit Capability Loss Factor, Nuclear Projects Review Commrttee (NPRC) HPSI, AFW, Emergency AC Power System, Unplanned Automate Scrams, Collective Radiation Exposure, Fuel C) Modification Requests being revewed by the Reliability, Thermal Performance, Secondary System Nuclear Projects Committee (NPC). Chemistry, and Industrial Safety Accident Rate.

These Modification Requests may be reviewed several times PREVENTABLE / PERSONNEL ERROR LERs before they are approved for accomphshment or canceled.

Some of these Modification Requests are retumed to This indicator is a breakdown of LERs. For purposes of LER Engineering for more informaton, some approved for event classificaton, a " Preventable LER* ls defined as:

evotuation, some approved for study, and some approved for planning. Once planning is completed and the scope of the An event for which the root cause is personnel error (i.e.,

work is clearty defined, these Modification Requests may be inapprooriate action by one or more individuals), inadequate approved for accomplishment with a year assigned for administrative controls, a design construction, installation, construction or they may be canceled. All of these different installation, fabrication problem (involving work completed phases require review. by or supervised by OPPD personnel) or a maintenance problem (attributed to inadequate or irnproper upkeep / repair

3) Design Engineering Backlog /in Progress. Nuclear of plant equipment). Also, the cause of the event must have Planning has assigned a year in which construction will occurred within approximately two years of the

Event Date" be completed and design work may be in progress. specified in the LER (e g., an event for which the cause is attributed to a prob lem with the enginal design of the plant

4) Construction Backlog /In Progress. The Construction would not be considered preventable).

Package has been issued or construction has begun but the modification has not been accepted by the System For purposes of LER eet classificaton, a " Personnel Error" Acceptance Committee (SAC) LER is defined as t- = vs:

5) Design Engineering Update Backlog /In Progress. An event for whch the root cause is inappropriate action on PED has received the Modification Completion Report but the part of one or more individuals (as opposed to being the drawings have not been updated, attnbuted to a department or a general group). Also, the 70 l

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e PERFORMANCE INDICATOR DEFINITIONS inappropriate action must have occurred within The number of Nuclear Plant Reliabihty Data System (NPRDS) approximately two years of the ' Event Date" specified in the components with more than one failure and the number of LER.

NPRDS components with more than two failures for the Additionally, each event classified as a ' Personnel Error" eighteen-month CFAR period.

should also be classifed as

Preventable." This indicator trends personnel performance for SEP ltem #15. SAFETY SYSTEM FAILURES PRIMARY SYSTEM LITHlUM % OF HOURS OUT OF LIMIT S1fety system failures are any events or conditions that could prevent the fulfillment of the safety functions of structures or The percent of hours out of hmit are for lithium divided by the systems. If a system consists of multiple redundant total number of hours possible for the month. subsystems or trains, failure of all trains constitutes a safety system failure. Failure of one of two or more trains is not PROCEDURAL NONCOMPLIANCE INCIDENTS counted as a safety system failure. The definition for the (MAINTENANCE) indicator parallels NRC reporting requirements in 10 CFR 50.T2 and 10 CFR 50.T3 The following is a list of the major The number of identified incidents concoming maintenance safety systems, sub-systems, and components monitored for procedural problems, the number of closed ira related to the this inddator-use of procedures (includes the number of closed irs caused by procedural noncompliance), and the number of closed Accident Monitoring instrumentation, Auxiliary (and procedural noncompliance irs. This indicator trends Emergency) Feedwater System, Combustible Gas Control, personnel performance for SEP #15,41 and 44. Component Coohng Water System, Containment and Containment Isolation, Containment Coolant Systems, PROGRESS OF CYCLE 17 OUTAGE MODIFICATION Control Room Emergency Ventilation System, Emergency PLANN89 Core Cooling Systems, Engineered Safety Features Instrumentation, Essential Compressed Air Systems, This indicator shows the status of modifications approved for Essential or Emergency Service Water, Fire Detection or completion during the Refueling Outage. Suppression - Systems, Isolation Condenser, Low Temperature Overpressure Protection, Main Steam Line PROGRESS OF 1996 0N-LINE MODIFICATION PLANNINC isolation Valves, Onsite Emergency AC & DC Power w/ Distribution, Radiation Monitonng Instrumentation, This indicator shows the status of modrfications approved for Reactor Coolant System, Reactor Core isolation Coohng completion dunng 1995. System, Reactor Tnp System and Instrumentation, Recirectation Pump Trip Actuation Instrumentation, 1 RADIOLOGICAL WORK PRACTICES PROGRAM Residual Heat Removal Systems, Safety Valves, Spent

, Fuel Systems, Standby Liquid Control System and Ultimate The nurnber of identified poor radiological work practices Heat Sink.

(PRWPs) for the reporting month. This indicator tracks radiological work performance for SEP #52. SECONDARY SYSTEM CHEMISTRY PERFORMANCE INDEX RATIO OF PREVENTIVE TO TOTAL MAINTENANCE &

PREVENTIVE MAINTENANCE ITEMS OVERDUE The Chemistry Performance index (CPI) is a calculation based on the concentration of key impunties in the secondary side of 8

The ratio c preventive maintenance (including surveillance the plant. These key impunties are the most hkely cause of testing and calibration procedures) to the sum of non-outage deterioration of the steam generators. Criteria for calculating corrective maintenance and preventive maintenance the CPI are:

completed over the reporting penod. The ratio, expressed as

a percentage, is calculated based on man-hours. Also 1) The plant is at greater than 30 percent power; and I displayed are the percent of preventive maintenance items in l the month that were not completed or administratively closed 2) the power is changing less than 5% per day.

by the scheduled date plus a grace period equal to 25% of the scheduled interval This indicator tracks preventive The CPIis calculated using the following equation:

maintenance actrvities for SEP #41.

CPI = ((sodium /0.79) + (Chloride /1.52) + (Sulfate /1.44) +

, RECORDABLE INJURY /lLLNESS CASES FREQUENCY (Ironf3.30) + (Copper /0.30)+(Condensate 02/2.90))/6 i

RATE Where: Sodium, sulfate, chloride and condensate dissolved The number of injunes requinng more than normal first aid per oxygen are the monthly average blowdown concentrations in 200,000 man-hours worked. This indicator trends personnel ppb, iron and copper are monthly tirne weighted average performance for SEP #15,25 and 26. feedwater concentrations in ppb. The denominator for each of the five factors is the INPO median value. If the monthly REPEAT FAILURES average for a specific parameter is less than the INPO median 71 l

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O PERFORMANCE INDICATOR DEFINITIONS value, the median value is used in the calculaton. 2) Jumpers and blocks which are installed for Surveillance Tests, Maintenance Procedures, Calibraton Procedures, SIGNIFICANT EVENTS Special Procedures or Operating Procedures are not mnsidered as temporary modificatens unless the jumper Significant events are the events identlied by NRC staff or block remains in place after the test or procedure is through detailed screening and evaluaton of operahng complete. Jumpers and blocks installed in test or lab experience. The screening process includes the daily review instruments are not considered as temporary and docussion of all reported operabng reactor events, as wen modifications.

as other operatonal data such as special tests or constructen activities. An event identrfied from the screening process as 3) Scaffold is not consioered a temporary modrncation.

a signifcant event candedate is further evaluated to determine Jumpers and blocks which are installed and for which MRs if any actual or potential threat to the health and safety of the have been submitted will be considered as temporary public was involved. Specific examples of the type of critena modificatons until final resolution of the MR and the are summarized as follows: Jumper or block is removed or is permanently recorded on

1) Degradaten of important safety equipment; the drawings. This indcator trads temporary modrhcations for SEP #62 and 71.

2) Unexpected plant response to a transient; THERMAL PERFORMANCE

3) Degradauon of fuel integnty, primary coolant pressure boundary, important associated features; The ratio of the design gross heat rate (corrected) to the adjusted actual gross heat rate, expressed as a percentane.

4) Scram with complication; UNIT CAPABILI1Y FACTOR

5) Unplanned release of radioactivity; The ratio of the available energy generation over a given time

6) Operation outside the hmits of the Technical period to the reference energy generation (the energy that Specifications; could be produced if the unit were operated continuously at fuH power under reference ambient conditions) over the same time

7) Other. period, expressed as a percentage.

INPO significant events reported in this indicator are SERs (Significant Event Reports) which inform utihties of significant events and lessons leamed identr!ied through the SEE-IN UNIT CAPACITY FACTOR screening process.

The net electrical energy generated (MWH) divided by the SPARE PARTS INVENTORY VALUE product of maximum dependable capacity (net MWe) times the gross hours in the reporting penod expressed as a percent.

The dollar value of the spare parts inventory for FCS during Net electreal energy generated is the gross electrical output the reporting period. of the unit measured at the output terminals of the turbine generator minus the normal station service loads during the STAFFING LEVEL gross hours of the reporting period, expressed in megawatt hours.

The actual staffing level and the authoi; zed staffing level for the Nuclear Operations Division, The Production Engineenng UNPt.ANNED AUTot4ATIC REACTOR SCRAMS PER 7,000 Division, and the Nuclear Services Division. This indcator CRITICAL HOURS trMts performance for SEP #24 The indcator is defined as the number of unplanned automatic STATION NET GENERATION scrams (RPS logic actuations) that occur per 7,000 hours0 days 0 hours 0 weeks 0 months of entcal operation.

The not generabon (sum) produced by the FCS dunng the reporbng month. The value for this indicator is calculated by multiplying the total number of unplanned automatic reactor scrams in a specific TEMPORARY MODIFICATIONS time period by 7,000 hours0 days 0 hours 0 weeks 0 months , then dividing that number by the total number of hours critcal in the same time period. The The number of temporary mechancai and electrical indicator is further defined as follows:

configurations to the plant's systems.

1) Unplanned rneans that the scram was not an anticipated

1) Tempo'ary configurations are defined as electrical part of a planned test.

jumpers, electncal blocks, mechanical jumpers, or mechanical blocks which are installed in the plant 2) Scram means the automabc shutdown of the reactor by a operabng systoms and are not shown on the latest revision rapid insertion of negative reactivity (e.g., by control rods, of the P&tD, schematic, connection, winng, or flow hquid injection system, etc.) that is caused by actuation of diagrams. the reactor protecton system. The signal may have 72

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PERFORMANCE INDICATOR DEFINITIONS resulted from exceeding a set point or spurious. Quartile Region IV plant.

3) Automatic rneans that the inttial signal that caused VOLUME OF LOW-LEVEL SOLID RADIOACTIVE WASTE actuation of the reactor protection system logic was provided from one of the sensor's monitoring plant This indicator is defined as the volume of low-level solid parameters and condrtions, rather than the manual scram radioactive waste actually shipped for burial. This indicator swtches or, manual turbine trip swtches (or push-buttons) also shows the volume of low level radioactive waste which is provided in the main control torm. In temporary storage, the amount of radioactive oil that has been shipped off-site for processing, and the volume of sohd

4) Critical rneans that during the s'eany-Me condition of the dry radioactrve waste which has been shipped off-site for reactor prior to the scram, the effective multiplicata (k , processing, Low-level solid radioactive waste consists of dry

) was essentially equal to one. achve waste, sludges, resins, and evaporator bottoms generated as a result of nuclear power plant operate and UNPLANNED CAPABILITY LOSS FACTOR maintenance. Dry radioactive waste indudes contaminated rags, cleaning matennis, disposable protective clothing, plastic The rabo of the unplanned energy losses dunng a given period containers, and any other matenal to be disposed of at a low-of time, to the reference enargy generabon (the energy that level radioactive waste disposal sde, except resin, sludge, or could te produced if the unit were operated continuously at full evaporator bottoms. Low-level refers to all radioactive waste power under reference ambent conddeons) over the same tirne that is not spent fuel or a by-product of spent fuel processing period, expressed as a percentage. This indicator tracks radiologbal work performance for SEP

$4 UNPLANNED SAFETY SYSTEM ACTUATIONS . (INPO

+ DEFINITION)

This indicator is defined as the sum of the following safety

! system actuations:

1) Tre number of unplanned Emergency Core Cooling System (ECCS) actuations that resut from reaching an ECCS actuation set point or from a spurious / inadvertent ECCS signal.

2) The number of unplanned emergency AC power system actuations that result from a loss of power to a safeguards

, bus. An unplanned safety system actuation occurs when an actuation set point for a safety system is reached or when a spunous or inadvertent signal is generated (ECCS only), and major equipment in the system is aduated.

Unplanned means that the system actuate was not part of a planned test or evolution. The ECCS actuations to be counted are actuations of the high pressure injection system, the low pressure injection system, or the safety injection tanks.

UNPLANNED SAFETY SYSTEM ACTUATIONS .(NRC DEFINITION)

The number of safety r ystem actuations which include (gdy) the Hign Pressure Safety injection System, the Low Pressure Safety injecuon System, the Safety injection Tanks, and the Emergency Diesel Generators. The NRC classification of safety system actuations includes actuations when major equipment is operated gng when the logic systems for the above safety systems are challenged.

VIOLATION TREND

~

This indicator is defined as Fort Calhoun Station Cited Violations and Non-Cited Violations trended over 12 months.

Additionally, Cited Violations for the top quartile Region IV plant is trended over 12 months (lagging the Fort Calhoun Station trend by 2 3 months). It is the Fort Calhoun Station goal to be at or below the cited violation trend for the top 73 l

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$AFETY ENHANCEMENT PROGRAM INDEX The purpose of the Safety Enhancement Program (SEP) Performance Indicators index is to list performance indicators related to SEP items with parameters that can be trended.

SEP Reference Number 15 Eagg !

. Increase HPES and IR Accountability through use of Perfonnance Indicators <

Procedural Noncompliance incidents (Maintenance) ..... . ... ....,.................. 43 !

Recordable injury / Illness Cases Frequency Rate .. . ....... ..................... 16 !

Clean Controlled Area Contaminations >1,000 Disintegrations / Minute Per Probe Area . . . . . . . . . 17 Preventable / Personnel Error LERs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 SEP Reference Numbers 25. 26. & 27

= Training Program for Managers and Supervisors implemented

. Evaluate and implement Station Standards for Safe Worn Practice Requirements

. Implement Supervisory Enforcement of Industrial Safety Standards Disabling injury /lllness Frequency Rate . . . . . ............. ......... ......,.... 15 Recordable injury /lliness Cases Frequency Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 SEP Reference Number 31

= Develop Outage and Maintenance Planning Manual and Conduct Project Management Training MWO Planning Status (Cycle 17 Refueling Outage) . .. . .... ...................... 59 SSED's Overall Project Status . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 60 Overall Project Status (Cycle 17 Refueling Outage) ..... . . ............ .. ,, .., 61 Progress of Cycle 17 Outage Modification Planning . . . . . . . . . . . . . . . . . . . . . , . . . . . 63 HE. Reference Number 33

. Develop On-Line Maintenance and Modification Schedule 1996 On-line Modification Planning . . . . , , . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . 62 SEP Reference Number 36

. Reduce Corrective Non-Outage Backlog Maintenance Workload Backlogs (Grrective Non-Outage) .. .... . .. . ....... .., . 39 SEP Refer 6nce Numb 9rs 41 & 44

. Develop and implement a Preventive Maintenance Schedule

. Compliance With and Use of Procedures Ratio of Preventive to Total Maintenance & Preventive Maintenance items Overdue ........... 40

- Procedural Noncompliance incidents (Maintenance) . . . . . . . . . . . . . . . .........., .... 43 SEP Reference Number 46

. Design a Procedures Control and Administrative Program Document Review . ...... ........ . . ..... . ., . . . .. ... . ... . 48 74

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SAFETY ENHANCEMENT PROGRAM INDEX SEP Reference Number 52 Page

. Establish Supervisory Accountability for Workers Radiological Practices Radiological Work Practices Program . . . . . . . . . . . . . . . . . . . . . .... .. . . . . , 47 SEP Reference Number 54

. Complete implementation of Radiological Enhancement Program Clean Controlled Area Disintegrations 2.1,000 Counts / Minute Per Probe Area . . . ...... . 17 1 Collective Radiation Exposure . . . . .... ............ . .. .. .. . 11 Volume of Low-Level Solid Radioactive Waste . . . . . . ... . .. . .. .. 12 Contaminated Radiation Controlled Area . . . ... . . ... . . ... .... . . .. . 46 SEP Reference Number 58

. Revise Physical Security Training and Procedure Program Loggable/ Reportable Incidents (Security) ... . . ........ . . .... ..... ... 49 SEP Reference Numbers 60 & 61

. Improve Controls Over Surveillance Test Program

. Modify Computer Program to Correctly Schedule Surveillance Tests Number of Missed Surveillance Tests resulting in Licensee Event Reports ...... ... ... 23 SEP Reference Number 62

. Establish Interim System Engineers Temporary Modifications ,. , . .,, , ,.. , . . .... .... .. . . .... 50 Engineer lng Assistance Request (EAR) Breakdown .... .. .. .... ...,..... . . 52 Engineering Change Notice Status . . .... ... , .... . . . , . . .. 53 Engineering Change Notices Open . . . . . . . . . . . ... . . .. . . ,, ,, , 54 SEP Reference Number 68

. Assess Root Cause of Poor Operator Training and establish means to monitor Operator Training License Operator Requalification Training . . . . . . . ... . .. . .. . . . 56 License Candidate Exams .... . .. ,. .. ... . ... ... , . . . . 57

. SEP Reference Number 71

. Improve Controls over Temporary Modifications Temporary Modifications .,,. ... .. . .. . .. . . . .. ,, ... 50 75 i

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ML20217D231

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